Novosibirsk Mirrors Past Present and Future

EPKruglyakov AVBurdakov GIDimov AAIvanov

Novosibirsk July 5 ndash 9 2010

Budker Institute of Nuclear Physics Novosibirsk Russia

8th International Conference on Open Magnetic Systems for Plasma Confinement

AUTHORS OF PROPOSAL OF PLASMA CONFINEMENT IN MIRROR TRAPS (1953)

THE FIRST EXPERIMENTS SNRodionov (Institute of Nuclear Physics) Atomnaya Energiya 6 pp 623 - 629 1959 IT WAS SHOWN THAT CHARGED PARTICLES MADE MORE THAN 107 REFLECTIONS FROM MIRRORS Gibson G Lawer EJ Bull Am Phys Soc v3 p412 1958

INSTITUTE OF NUCLEAR PHYSICS HAS STUDIED PHYSICS OF MIRRORSPRACTICALLY SINCE ITS FOUNDATION (1958)

PLASMA PHYSICS ACTIVITY OF NOVOSIBIRSK IN THE SIXTIES

(SELECTED WORKS)

THE MOST IMPORTANT RESULTS OBTAINED BY THEORISTS OF THE ldquoFIRST GENERATIONrdquo

RZSAGDEEV PREDICTION OF EXISTANCE OF COLLISIONLESS SHOCK WAVES (Sov JTP v 31 10 p1185 1961)

AAGALEEV PREDICTION OF INSTABILITY LINKED WITH ldquoLOSS CONErdquo IN MIRRORS (Sov JETP v49 2(8) p672 1965)

AAGALEEV RZSAGDEEV DISCOVERY OF ldquoNEOCLASSICAL DIFFUSIONrdquo (Sov JETP v 53 1 p343 1967)

VEZAKHAROV PREDICTION OF COLLAPS OF LANGMUIRE WAVES (Sov JETP v62 5 p 1745 1972)

EARLY EXPERIMENTS WITH ALCALINE PLASMA (Q-MACHINE)

TYPICAL ALCALINE PLASMA HAS A DENSITY OF 109- 1010 cm-3 AND

PLASMA TEMPERATURE T asymp 03 eV BUT BECAUSE OF λinfinT2ne MANY

PHYSICAL PHENOMENA IN A ldquoDENSErdquo (1013 - 1015 cm-3) PLASMA

COULD BE STUDIED IN Q-MACHINE

-THE MOST IMPORTANT RESULTS OBTAINED IN NOVOSIBIRSK

1 OBSERVATION OF ldquoUNIVERSALrdquo INSTABILITY IN RADIALLY

INHOMOGENEOUS POTASSIUM PLASMA IN MAGNETIC FIELD

NSBuchelnikova Nuclear fusion v4 pp165-168 1964

2 E - BEAM ndash PLASMA INTERACTION WITH POTASSIUM PLASMA

OBSERVATION OF ELECTRON HEATING AND PLASMA TURBULENCE

VTAstrelin NSBuchelnikova AADrozdov et al Sov JETP v58 pp1553 ndash

1556 1970

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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AUTHORS OF PROPOSAL OF PLASMA CONFINEMENT IN MIRROR TRAPS (1953)

THE FIRST EXPERIMENTS SNRodionov (Institute of Nuclear Physics) Atomnaya Energiya 6 pp 623 - 629 1959 IT WAS SHOWN THAT CHARGED PARTICLES MADE MORE THAN 107 REFLECTIONS FROM MIRRORS Gibson G Lawer EJ Bull Am Phys Soc v3 p412 1958

INSTITUTE OF NUCLEAR PHYSICS HAS STUDIED PHYSICS OF MIRRORSPRACTICALLY SINCE ITS FOUNDATION (1958)

PLASMA PHYSICS ACTIVITY OF NOVOSIBIRSK IN THE SIXTIES

(SELECTED WORKS)

THE MOST IMPORTANT RESULTS OBTAINED BY THEORISTS OF THE ldquoFIRST GENERATIONrdquo

RZSAGDEEV PREDICTION OF EXISTANCE OF COLLISIONLESS SHOCK WAVES (Sov JTP v 31 10 p1185 1961)

AAGALEEV PREDICTION OF INSTABILITY LINKED WITH ldquoLOSS CONErdquo IN MIRRORS (Sov JETP v49 2(8) p672 1965)

AAGALEEV RZSAGDEEV DISCOVERY OF ldquoNEOCLASSICAL DIFFUSIONrdquo (Sov JETP v 53 1 p343 1967)

VEZAKHAROV PREDICTION OF COLLAPS OF LANGMUIRE WAVES (Sov JETP v62 5 p 1745 1972)

EARLY EXPERIMENTS WITH ALCALINE PLASMA (Q-MACHINE)

TYPICAL ALCALINE PLASMA HAS A DENSITY OF 109- 1010 cm-3 AND

PLASMA TEMPERATURE T asymp 03 eV BUT BECAUSE OF λinfinT2ne MANY

PHYSICAL PHENOMENA IN A ldquoDENSErdquo (1013 - 1015 cm-3) PLASMA

COULD BE STUDIED IN Q-MACHINE

-THE MOST IMPORTANT RESULTS OBTAINED IN NOVOSIBIRSK

1 OBSERVATION OF ldquoUNIVERSALrdquo INSTABILITY IN RADIALLY

INHOMOGENEOUS POTASSIUM PLASMA IN MAGNETIC FIELD

NSBuchelnikova Nuclear fusion v4 pp165-168 1964

2 E - BEAM ndash PLASMA INTERACTION WITH POTASSIUM PLASMA

OBSERVATION OF ELECTRON HEATING AND PLASMA TURBULENCE

VTAstrelin NSBuchelnikova AADrozdov et al Sov JETP v58 pp1553 ndash

1556 1970

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 58
• Slide 59
• Slide 60
• Slide 61

PLASMA PHYSICS ACTIVITY OF NOVOSIBIRSK IN THE SIXTIES

(SELECTED WORKS)

THE MOST IMPORTANT RESULTS OBTAINED BY THEORISTS OF THE ldquoFIRST GENERATIONrdquo

RZSAGDEEV PREDICTION OF EXISTANCE OF COLLISIONLESS SHOCK WAVES (Sov JTP v 31 10 p1185 1961)

AAGALEEV PREDICTION OF INSTABILITY LINKED WITH ldquoLOSS CONErdquo IN MIRRORS (Sov JETP v49 2(8) p672 1965)

AAGALEEV RZSAGDEEV DISCOVERY OF ldquoNEOCLASSICAL DIFFUSIONrdquo (Sov JETP v 53 1 p343 1967)

VEZAKHAROV PREDICTION OF COLLAPS OF LANGMUIRE WAVES (Sov JETP v62 5 p 1745 1972)

EARLY EXPERIMENTS WITH ALCALINE PLASMA (Q-MACHINE)

TYPICAL ALCALINE PLASMA HAS A DENSITY OF 109- 1010 cm-3 AND

PLASMA TEMPERATURE T asymp 03 eV BUT BECAUSE OF λinfinT2ne MANY

PHYSICAL PHENOMENA IN A ldquoDENSErdquo (1013 - 1015 cm-3) PLASMA

COULD BE STUDIED IN Q-MACHINE

-THE MOST IMPORTANT RESULTS OBTAINED IN NOVOSIBIRSK

1 OBSERVATION OF ldquoUNIVERSALrdquo INSTABILITY IN RADIALLY

INHOMOGENEOUS POTASSIUM PLASMA IN MAGNETIC FIELD

NSBuchelnikova Nuclear fusion v4 pp165-168 1964

2 E - BEAM ndash PLASMA INTERACTION WITH POTASSIUM PLASMA

OBSERVATION OF ELECTRON HEATING AND PLASMA TURBULENCE

VTAstrelin NSBuchelnikova AADrozdov et al Sov JETP v58 pp1553 ndash

1556 1970

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 59
• Slide 60
• Slide 61

THE MOST IMPORTANT RESULTS OBTAINED BY THEORISTS OF THE ldquoFIRST GENERATIONrdquo

RZSAGDEEV PREDICTION OF EXISTANCE OF COLLISIONLESS SHOCK WAVES (Sov JTP v 31 10 p1185 1961)

AAGALEEV PREDICTION OF INSTABILITY LINKED WITH ldquoLOSS CONErdquo IN MIRRORS (Sov JETP v49 2(8) p672 1965)

AAGALEEV RZSAGDEEV DISCOVERY OF ldquoNEOCLASSICAL DIFFUSIONrdquo (Sov JETP v 53 1 p343 1967)

VEZAKHAROV PREDICTION OF COLLAPS OF LANGMUIRE WAVES (Sov JETP v62 5 p 1745 1972)

EARLY EXPERIMENTS WITH ALCALINE PLASMA (Q-MACHINE)

TYPICAL ALCALINE PLASMA HAS A DENSITY OF 109- 1010 cm-3 AND

PLASMA TEMPERATURE T asymp 03 eV BUT BECAUSE OF λinfinT2ne MANY

PHYSICAL PHENOMENA IN A ldquoDENSErdquo (1013 - 1015 cm-3) PLASMA

COULD BE STUDIED IN Q-MACHINE

-THE MOST IMPORTANT RESULTS OBTAINED IN NOVOSIBIRSK

1 OBSERVATION OF ldquoUNIVERSALrdquo INSTABILITY IN RADIALLY

INHOMOGENEOUS POTASSIUM PLASMA IN MAGNETIC FIELD

NSBuchelnikova Nuclear fusion v4 pp165-168 1964

2 E - BEAM ndash PLASMA INTERACTION WITH POTASSIUM PLASMA

OBSERVATION OF ELECTRON HEATING AND PLASMA TURBULENCE

VTAstrelin NSBuchelnikova AADrozdov et al Sov JETP v58 pp1553 ndash

1556 1970

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
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• Slide 59
• Slide 60
• Slide 61

EARLY EXPERIMENTS WITH ALCALINE PLASMA (Q-MACHINE)

TYPICAL ALCALINE PLASMA HAS A DENSITY OF 109- 1010 cm-3 AND

PLASMA TEMPERATURE T asymp 03 eV BUT BECAUSE OF λinfinT2ne MANY

PHYSICAL PHENOMENA IN A ldquoDENSErdquo (1013 - 1015 cm-3) PLASMA

COULD BE STUDIED IN Q-MACHINE

-THE MOST IMPORTANT RESULTS OBTAINED IN NOVOSIBIRSK

1 OBSERVATION OF ldquoUNIVERSALrdquo INSTABILITY IN RADIALLY

INHOMOGENEOUS POTASSIUM PLASMA IN MAGNETIC FIELD

NSBuchelnikova Nuclear fusion v4 pp165-168 1964

2 E - BEAM ndash PLASMA INTERACTION WITH POTASSIUM PLASMA

OBSERVATION OF ELECTRON HEATING AND PLASMA TURBULENCE

VTAstrelin NSBuchelnikova AADrozdov et al Sov JETP v58 pp1553 ndash

1556 1970

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 61

-DEVELOPMENT OF BASIC DIAGNOSTICS FOR PLASMA STUDY 1 OPTICAL DIAGNOSTICS

INSTITUTE OF NUCLEAR PHYSICS WASTHE FIRST IN THE SOVIET UNION ANDONE OF THE FIRST IN THE WORLD WHERE DIFFERENT LASER DIAGNO-STIC METHODS (OPTICAL INTER-FEROMETRY AND THOMSON SCAT-TERING) WERE APPLIED (1964-1965)2 NEUTRAL BEAM INJECTORS FOR PLASMA STUDIES THE HISTORY OF NEUTRAL BEAM INJECTORS STARTED FROM THEPAPER OF GIBudker GIDimov rdquoCharge Exchange Injection of Protons into Circular Acceleratorrdquo Proceedings of the International Conference on High Energy Accelerators Dubna 1963 ATOMIZDAT Moscow 1964 pp 993-996PROPOSAL AND THE FIRST EXPERIMENT ON STUDY OF LOCALPLASMA PARAMETERS WITH THE USE OF NB INJECTORS (Eb= 15 keVIb = 03A db = 3 cm Δt = 2middot10-4 s) AMKudryavtsev AFSorokin Sov JETPLetters v18 8 pp486-490 19731973-1974 DIAGNOSTIC INJECTORS DINA-1 AND DINA-2 (EB ~ 25 keV IB ~ 1 A) WERE WORKED OUT BY DIMOV GROUP AND WERE DISTRI-BUTED AMONG FUSION LABORATORIES OF THE SOVIET UNION

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 59
• Slide 60
• Slide 61

BLACK CLOUDS 0VER CLASSICAL MIRRORS

bull FIRST YEARS ATTENTION OF PLASMA PHYSICISTS FIRST OF ALL WAS DIRECTED TO MIRRORS BUThellipbull IN 1960 FLUTE INSTABILITY PREDICTED PREVIOUSLY BY ROSENBLUTH AND KADOMTSEV WAS EXPERIMENTALLY OBSERVED (MSIoffe et al Sov JETP Letters v39 p1602 1960) GREAT DESPONDENCY APPEARED AMONG PLASMA PHYSICISTS HOW- EVER IN 1961 (Intern Conf of IAEA Zaltsburg 1961) MS IOFFE HAS DECLARED THAT THE INSTABILITY CAN BE SUPPRESSED (IOFFE BARS)

bull AA GALEEV (Sov JETP v 49 2 (8) p 672 1965) AND RPOST WITH

MN ROSENBLUTH (Phys Fluids v 9 p 730 1966) HAVE PREDICTED INSTABILITIES LINKED WITH ldquoLOSS CONErdquo IN MIRRORS bull ANALYSIS OF ENERGY BALANCE OF MIRROR TYPE FUSION REACTOR MADE BY DV SIVUKHIN HAS SHOWN VERY BAD PROSPECTS OF THIS SCHEME EVEN WITHOUT TAKING INTO ACCOUNT OF LOSS CONE INSTABILITIES (DVSivukhin In ldquoReview of Plasma Physicsrdquo v4 Consultants Bureau NY p 93 1966 DVSivukhin In ldquoVoprosy Teorii Plasmy v5 p 4391967 Moscow ATOMIZDAT)

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 56
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• Slide 58
• Slide 59
• Slide 60
• Slide 61

THE FIRST SERIOUS REVISION OF MIRROR CONCEPTSHAS OCCURRED IN 1971 ndash 1972

PROPOSAL OF MULTI-MIRROR CONCEPT OF LONGITUDINAL PLASMA CONFINEMENT

GIBudker VVMirnov DDRyutov Sov JETP Letters v14 p 320 1971

BGLogan MALieberman AJLichtenberg AMakhijani Phys RevLett v28 p144 1972

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 59
• Slide 60
• Slide 61

PRINCIPLES OF MULTI-MIRROR CONFINEMENT

R2 L2

i VTi

= R2 Li

LVTi

0 (λltltL)

ℓltλ

Gain is more than 102

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 61

PLASMA CONFINEMENT IN MULTI-MIRROR MAGNETIC FIELDS (Experiment with alcaline plasma)

GIBudker VVDanilov EPKruglyakov et al Sov JETP Lett v17 p117 1973

VVDanilov EPKruglyakov Sov JETPv68 6 p2109 1975

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 61

Physics of transverse ldquowall confinementrdquo(TRANSVERSE MAGNETIC CONFINEMENT OF VERY DENSE PLASMA

(n ~ 1017 - 1018 cm-3) REQUIRES MAGNETIC FIELD STRENGTH OF SEVERAL MEGAGAUSS)

Vekshtein GE Mirnov VV Ryutov DD Chebotaev Journ of AppliedMechanics and Technical Physics 6 p3 (1974)

τE asymp a2χ

Plasma and magnetic field behavior after pulsed heating of plasma placed into tube from well conducting metall

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
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• Slide 13
• Slide 14
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• Slide 16
• Slide 17
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• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE MOST HIGH POWER SOURCE FOR HEATING CAN BE BUILT ON THE BASIS OF HIGH CURRENT RELATIVISTIC ELECTRON BEAM (REB)

BUThellip

AT ANY RESONABLE LONGITUDINAL SIZE L OF MAGNETIC SYSTEM WITH PLASMA THE COULOMB MEAN FREE PATH OF RELATIVISTIC

ELECTRONS λe WILL BE LARGER THAN SYSTEM SIZE

λe gtgt L ONE COULD HOPE ONLY ON MICROINSTABILITIES

THE FIRST EXPERIMENTS ON PLASMA HEATING BY REB WERE MADE IN 1972

VSKoidan VMLagunov VNLukyanov et al Proc 5th Europ Conf on Controlled Fusion and Plasma Physics v1 p161 Grenoble 1972 AVAbrashitov AVBurdakov VSKoidan et al Sov JETP Lett v18 p675 1973

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
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• Slide 59
• Slide 60
• Slide 61

INAR Eb~1MeV Ib ~ 5 kA τb ~ 50 ns

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
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• Slide 14
• Slide 15
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• Slide 17
• Slide 18
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• Slide 21
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• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
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• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

HOW TO HEAT A DENSE PLASMA IN LONG LINEAR SYSTEM

THE FIRST RESULTS HAVE SHOWN PRINCIPLE POSSIBILITY TO USE REBs FOR DENSE PLASMA HEATING BUT PARAMETERS OF REB

(Eb = 1 MeV Ib = 5 kA τb = 50 -70 ns Q asymp 300 J) WERE TOO FAR FROM REQUIREMENTS OF FUSION TECHNOLOGIES

SPECIAL PROGRAM OF DEVELOPMENT OF POWERFUL REB

GENERATORS WAS ARRANGED IN THE INSTITUTE

1 APPLICATION OF ULTRA-PURE WATER AS A HIGH-VOLTAGE INSULATOR ( = 80)

SEVERAL GENERATORS WERE CONSTRUCTED AND TESTED IN THE INSTITUTE

2 ALABORATION OF HIGH POWER MICROSECOND REBs

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 59
• Slide 60
• Slide 61

1975 GOL - 1 - AN INSTALLATION FOR STUDY OF REB - PLASMA INTERACTION THE FIRST ACCELERATOR WITH WATER INSULATION WAS USED HERE Qb =1-2 kJ

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
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• Slide 37
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• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
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• Slide 46
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• Slide 59
• Slide 60
• Slide 61

ACCELERATOR AQUAGEN ON THE BASIS OF WATER INSULATION

(Eb = 1 МeV Ib = 300 кА Qbasymp 25 kJ) 1977

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
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• Slide 46
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• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

DEVELOPMENT OF HIGH POWER MICROSECOND BEAMS

ACCELERATOR U-1 (LAST VERSION)

1982 First version of generatorQb=22 kJ Eb = 05 MeV Ib asymp50 kA τb asymp25 mcsSV Lebedev VV Chikunov MA Scheglov Sov JTP Letters v8 11 p 693 1982

1987 Qb max = 130 kJ Eb = 1 MeV Ib = 60 kA after magnetic compression jb = 5 kAcm2 τb asymp 45 mcsSGVoropaev BAKnyazev VSKoidan Sov JTP Lett v13 7 p 431 1987

Present day parameters of microsecond beamsQb = 300 kJ Ub = 1 MeV Ib = 40 kA τb asymp 8 mcs

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 3
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• Slide 6
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• Slide 21
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• Slide 24
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• Slide 26
• Slide 27
• Slide 28
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• Slide 30
• Slide 31
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• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

THE MOST IMPORTANT EXPERIMENTAL RESULTS ON REB -PLASMA INTERACTION AND STUDY OF MULTI-

MIRROR HOT PLASMA CONFINEMENT

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
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• Slide 13
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• Slide 22
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• Slide 24
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• Slide 26
• Slide 27
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• Slide 30
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• Slide 33
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• Slide 37
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• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
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• Slide 46
• Slide 47
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• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

GOL-M STUDY OF NATURE OF REB-PLASMA INTERACTION

THE FIRST DIRECT EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIRE TURBULENCE CONTAINS IN Vyacheslavov LN Kandaurov IV Kruglyakov EP et al Sov JETP Lett v50 9 p 379 1989

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
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• Slide 30
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• Slide 33
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• Slide 37
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• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
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• Slide 46
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• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

EXPERIMENTAL EVIDENCE OF EXCITATION OF EXPERIMENTAL EVIDENCE OF EXCITATION OF STRONG LANGMUIR TURBULENCESTRONG LANGMUIR TURBULENCE

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

0 10 20 300

15105

WkTe

Точность абсолютныхизмерений

1105

5104

kvbpe

Precision of absolute measurements

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 37
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• Slide 39
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• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

PLASMA HEATING AND CONFINEMENT ON MULTI-MIRROR TRAP GOL-3

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

GOL-3 facility

planar beam diode

U-2 generator of the electron beam

corrugated magnetic fieldexit unit

plasma

PlasmaLength ~ Density -

12 m1 0 - 10 m20 22 -3

Magnetic fieldSolenoid - Mirrors - 10 TCapacity storage -

5 T

200 MJ

Electron beamE n e r g y - 1 M e VC u r r e n t - 5 0 k AE n e r g y c o n t e n t - P u l s e d u r a t i o n - 8 micro s

0 3 M J

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 3
• Slide 4
• Slide 5
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• Slide 53
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• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

EFFICIENCY OF REB ndash PLASMA INTERACTION

INAR

FROM 1972 UP TO 1988 MAXIMUM EFFICIENCY HAS ACHIEVED 40

Arzhannikov AV Burdakov AV Kapitonov VA et al Plasma Physics and Controlled Fusion v30 11 p 1571 1988

GOL ndash 3

AT PRESENT MAXIMUM EFFICIENCY IS 50Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference on

Plasma Physics Dublin Ireland 21-26 June 2010

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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• Slide 61

Plasma heating by REB in homogeneous (a) and multi- mirror (b) geometry

Time behavior of plasma pressure at ne =15middot1015 cm-3 z = 208m

03P

O0

06F

0 02 04 06 08tim e m s

0

04

08

12

16

neT

e+n i

Ti

1015

keV

cm

3

pl5871

Electron component

Ion component

a

b

time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
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time ms

DD neutron irradiation after REB plasma- interaction

At present nτmax asymp 2middot1018m-3middots

Intensity

Several diagnostics gave the meaning of temperature OF Ti asymp 2 keV

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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• Slide 61

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCTIVITY

Astrelin VT Burdakov AV Postupaev VV Plasma Physics Reports v24 p414 (1998)

Arzhannikov AV Astrelin VN Burdakov AV et al JETP Letters v77 p358 (2003)

Direct demonstration of the suppression effect

bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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bull CORRAGATION OF MAGNETIC FIELD ALONG THE SYSTEM LENGTH LEADS TO INHOMOGENEOUS HEATING OF PLASMA ELECTRONS BY REB (BECAUSE OF Γinfinnb)

bull THE PRESSURE GRADIENTS BETWEEN PLAGS AND MID PLANE IN

EACH CELL LEAD TO PLASMA EXPANSION FROM PLAGS IN BOTH DIRECTIONS AS A RESULT OF THAT ION HEATING APPEARS

GOL-3 WHY THE IONS ARE HEATING

Гinfin (nb ne)ώpe

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
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• Slide 33
• Slide 34
• Slide 35
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• Slide 37
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• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
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• Slide 46
• Slide 47
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• Slide 49
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• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

20 30 40

ремя микросекунд

PL5741

TIME microsecond

T asymp LVTi

Time behavior of neutron radiation from separate mirror cell of GOL-3

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 59
• Slide 60
• Slide 61

EXCITATION OF DENSITY OSCILATIONS IN SEPARATE CELLS - BOUNCE INSTABILITY

Ti2Ti1

Ti1 gt Ti2

iT Tl

Vi ~

Beklemishev AD Fusion Science and Technology Trans v 51 2T P180 2007

α2gtα

α1lt α

DECELERATION OF IONS CAN LEAD TO THEIR CAPTURE

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
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• Slide 14
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• Slide 24
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• Slide 26
• Slide 27
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• Slide 30
• Slide 31
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• Slide 33
• Slide 34
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• Slide 36
• Slide 37
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• Slide 41
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• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

ABOUT TRANSVERSE HEAT LOSSES OF HOT PLASMA

SUPPRESSION OF LONGITUDINAL ELECTRON THERMAL CONDUCT-

ANCE IS EXPLAINED BY SIGNIFICANT (SEVERAL THOUSANDS TIMES) INCREASE OF COLLISION FREQUENCY OF PLASMA ELECTRONS

HOWEVER THE SAME EFFECT SHOULD INCREASE THE TRANSVERSE HEAT LOSSES

FORTUNATELY SPECIAL EXPERIMENTS WITH THIN REB (D asymp 1cm INSTEAD OF USUALLY USED BEAM WITH D asymp 5 cm) HAVE SHOWN THAT SPECIFIC PARAMETERS OF PLASMA AFTER HEATING DOES NOT CHANGE IT MEANS THAT TRANSVERSE HEAT LOSSES UP TO NOW ARE NEGLIGIBLE

Postupaev VV Arzhannikov AV Astrelin VT et al 37th EPS Conference onPlasma Physics Dublin Ireland 21-26 June 2010

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 20
• Slide 21
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• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
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• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
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• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

Generator of oncoming beam

Eb ~ 100 keV

Ib ~ 1 kA

Jb ~ 1 kAcm2

τb ~ 01 ndash 1 ms

GOL-3 NEAREST FUTURE PLANS INJECTION OF ONCOMING BEAM TO OBTAIN SUPPRESSION OF ELECTRON THERMAL CONDUCTION OF HIGH TEMPERATURE PLASMA DURING LONG TIME (01 ndash 1 ms)

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

CONCEPT OF AMBIPOLAR CONFINEMENT(TANDEM MIRRORS)

Dimov GI Zakaidakov VV Kishinevskii ME Sov Journ of Plasma Physics v2 p 326 1976

Fowler TK Logan BG Comm Plasma Phys and Controlled Fusion v11 p 167 1977

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 10
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• Slide 17
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• Slide 20
• Slide 21
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• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
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• Slide 53
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• Slide 55
• Slide 56
• Slide 57
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• Slide 59
• Slide 60
• Slide 61

AMBIPOLAR TRAP

Ambipolar barrier eφc= kTemiddotln(npns)

τ~ τiimiddot(eφckTi)exp(eφckTi) При eφc gtgt kTe τ gtgt τii

ne np φs

i n(z) e

φc

φe

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

TANDEM MIRRORSmiddotIT TURNED OUT THAT TSUKUBA UNIVERSITY AND LIVERMORE middotLABORATORY WERE MORE READY TO CONSTRUCT THE AMBIPOLAR TRAPS THE FIRST DEMONSTRATION OF AMBIPOLAR PLASMA CONFINEMENT WAS PRESENTED BY Miyoshi S Yatsu K Kawabe T et alON THE 7th Intern Conf of IAEA (Vienna IAEA 1979 v2 p 437 USING 2XIIB AS END MIRRORS LIVERMORE PHYSICISTS DESIGNED AMBIPOLAR TRAP TMX WITH MORE HIGH PARAMETERS (n asymp 1012 cm-3

Тe asymp 200 eV β = 04 φс=300 V) IT WAS STARTED UP IN 1979 AND HAS DEMONSTRATED NINEFOLD GROWTH OF CONFINEMENT TIME τasymp 9τii

TMX

middotTHE DESIGN OF THE NOVOSIBIRSK AMBIPOLAR TRAP AMBAL WITH min B HAS STARTED IN 1977 HOWEVER AFTER SHORT CIRCUIT IN ONE OF END MIRRORS IT WAS DECIDED NOT TO RECONSTRUCT AMBAL BUT TO BUILT NEW FULLY AXISYMMETRIC SYSTEM AMBAL-M

HOWEVER AFTER BREAKUP OF THE SOVIET UNION IT WAS IMPOSSIBLE TO CONSTRUCT LARGE INSTALLATION FOR REASONABLE TIME

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
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• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
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• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

AXISYMMETRIC VERSION OF AMBIPOLAR TRAP AMBAL-M WITH MHD STABILIZATION BY END SEMICUSPS CONDUCTING WALLS FLR etc

THIS DESIGN WAS IMPLEMENTED ONLY BY 50

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
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• Slide 17
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• Slide 21
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• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
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• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
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• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
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• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
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• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

AMBAL-M (50 READINESS)

BECAUSE OF VERY LIMITED RESOURCES OF THE INSTITUTE IN 90s CONSTRUCTION OF AMBAL-M WAS STOPPED

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 10
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• Slide 17
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• Slide 21
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• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
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• Slide 30
• Slide 31
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• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

AMBALTHE MOST IMPORTANT RESULTS

bull EXPERIMENTS WITH NONAXISYMMETRIC END MIRROR OF AMBAL HOT DEUTERIUM PLASMA (Ti ~ 900 eV ne ~ 1013cm-3 ) WAS OBTAINED IN RESULT OF EXCITATION OF KELVIN ndash HELMHOLTZ INSTABILITY

APPEARED DURING PLASMA INJECTION FROM PLASMA GUNbull MHD STABLE PLASMA WAS OBTAINED IN LONG CENTRAL TRAP OF FULLY AXISYMMETRIC AMBAL-M (12) THE PARAMETERS OF THAT PLASMA WERE AS FOLLOWS ION TEMPERATURE Ti asymp 200 ndash 300 eV ELECTRON TEMPERATURE Te asymp 50 -70 eV

PLASMA DENSITY ne asymp 3middot1013 cm-3

PLASMA DIMENSIONS L asymp 6 m D asymp 40 cmbull DECAYING QUIESCENT PLASMA HAS TRANSVERSE DIFFUSION COEFFICIENT CLOSE TO CLASSICAL ONE

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
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• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

GAS DYNAMIC PLASMA CONFINEMENT

VVMirnov DDRyutov Sov JTP Lett v5 p678 1979

λii L ( more exact λii R L) R = Bm B0 = S0 Sm τ asymp nLS0 nVTiSm = RLVTi

VERY SIMPLE PHYSICS ABSENCE OF MICRO-INSTABILITIES IN COLLISIONAL PLASMA DISADVANTAGE TOO LARGE LENGTH OF FUSION REACTOR (OF THE ORDER OF 3-5 KILOMETERS) BUThellip THERE IS USEFUL APPLICATION OF THIS SCHEME AT PRESENT

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

POWERFUL 14 MeV NEUTRON SOURSE ON THE BASIS OF GDT Kotelnikov IA Mirnov VV Nagorny VP Ryutov DD Plasma Physics and Controlled Fusion Research 2 IAEA Vienna p309 1985

Z

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

-ARGUMENTS IN FAVOR OF NEUTRON SOURCE ON THE BASIS OF THE GAS DYNAMIC TRAP

bull THE GDT NS HAS THE SIMPLEST VACUUM AND MAGNETIC SYSTEMS BECAUSE OF AXISYMMETRIC GEOMETRYbull PLASMA PRESSURE IS COMPARABLE WITH MAGNETIC ONE IT MAKES POSSIBLE TO OBTAIN THE HIGHEST DENSITY OF NEUTRON FLUX FROM UNIT OF VOLUME IN COMPARISON WITH ANY OTHER SCHEMES OF NEUTRON SOURCESbull INTENSITY OF NEUTRON FLUX IS HIGH ONLY IN OPERATION ZONES THUS THE MAIN PART OF THE NEUTRON SOURCE CAN FUNСTION MANY YEARS WITHOUT REPLACEMENTbull NB INJECTORS WORK IN SIGNIFICANTLY MORE FAVORABLE CONDITIONS THAN THOSE IN TOKAMAK SCHEMESbull THE PROBLEM OF DISRUPTION DOES NOT EXISTbull THERE ARE NO DIVERTOR PROBLEMS

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

SOME COMMENTS ON EXCITATION OF MICROINSTABILITIES IN GDT PLASMA

IN PRINCIPLE NB INJECTION INTO ldquoWARMrdquo PLASMA CAN LEADTO EXCITATION OF MICROINSTABILITIES AND TO DECREASEOF FAST IONS LIFETIME CORRESPONDINGLY THE TOTAL NEUTRON FLUX WILL ALSODECREASE THAT IS WHY WE SHOULD SELECT THE BEAM ANDPLASMA PARAMETERS IN THE RANGE WHERE THE MICRO-INSTABILITIES HAVE NOT BEEN OBSERVED YETTO AVOID MICROINSTABILITIES SOME RESULTS OBTAINED AT2XIIB WHERE THEY DID NOT EXCITE WERE TAKEN INTOACCOUNT

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

COMPARISON OF DIMENSIONLESS PARAMETERS OF 2XIIB WITH THE TURNING POINT PARAMETERS OF THE GDT BASED NEUTRON SOURCE

PARAMETERS 2XIIB GDT NS

EINJ Te 100 100

ωpi ωBi 120 120 (D) 150 (T)

a ρ 25 67 (D) 54 (T)

ncold nhot 005 - 01 01

β 01 ndash 10 06IN 2XIIB CASE IN THE RANGE OF PARAMETERS PRESENTEDHERE MICROINSTABILITIES WERE NOT OBSERVED ONE SHOULDEXPECT THE SAME RESULT IN THE CASE OF GDT NS

middotIN THE MOST OF NEUTRON SOURCE VERSIONS ANALIZED IN

NOVOSIBIRSK Te VALUE SUPPORTED ON THE LEVEL OF 10-2 EINJ

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
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• Slide 16
• Slide 17
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• Slide 21
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• Slide 23
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• Slide 28
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• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

EXAMPLES OF CALCULATIONS OF GDT

BASED NEUTRON SOURCE PARAMETERS

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
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• Slide 17
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• Slide 19
• Slide 20
• Slide 21
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• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

FOR STANDARD CALCULATIONS OF NEUTRON SOURCEPARAMETERS THE FOLLOWING ONES ARE FIXED AS A RULE

bull ELECTRIC POWER CONSUMPTION FROM THE GRID (USUALLY) IS FIXED We = 60 MW

bull TOTAL POWER OF NEUTRON FLUX W = 2 MW IS ALSO FIXED

bull MAGNETIC FIELD IN MIRRORS Bm = 15 T MIRROR RATIO R = 15

bull INJECTION ANGLE θ = 300 bull INJECTION ENERGY OF D AND T EINJ = 65 keV THIS ENERGY IS OPTIMUM (see later)

bull PLASMA DIAMETER AT THE MIDPLANE 2a = 20 cm

bull RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY OF DT ATOMS Te EINJ = 10 -2

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

OPTIMIZED DENSITY OF NEUTRON FLUX VERSUS INJECTION ENERGY FOR DIFFERENT ELECTRON TEMPERATURES

Eoptimal asymp 65 keV

Te=2 keV

Te= 1 keV

Te=05keV

Te =02keV

Einj keV

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

NEUTRON FLUX DENSITY AS A FUNCTION OF

ELECTRON TEMPERATURE

Pn МWm2

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

basic version

01234567

0 1 2 3 4

Te (keV)

P M

Wbasic version

Pn

Neutron Flux Density vs Electron Temperature in the Absence of Microturbulences (If there are no limitation on TeEb ratio)

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21
• Slide 22
• Slide 23
• Slide 24
• Slide 25
• Slide 26
• Slide 27
• Slide 28
• Slide 29
• Slide 30
• Slide 31
• Slide 32
• Slide 33
• Slide 34
• Slide 35
• Slide 36
• Slide 37
• Slide 38
• Slide 39
• Slide 40
• Slide 41
• Slide 42
• Slide 43
• Slide 44
• Slide 45
• Slide 46
• Slide 47
• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

GDT

SOME EXPERIMENTAL RESULTS

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
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• Slide 42
• Slide 43
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• Slide 45
• Slide 46
• Slide 47
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• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

GAS DYNAMIC TRAP (GDT)GAS DYNAMIC TRAP (GDT)

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
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• Slide 4
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• Slide 46
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• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

NEUTRON FLUX DENSITY PROFILE (D-D REACTIONS) IN THE VICINITY OF TURNING POINT IN GDT

Pn au

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
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• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

β VALUE AS A FUNCTION OF ENERGY CONTENT OF FAST IONS IN HYDROGEN PLASMA (D0 -BEAMS)

β

Q kJ

β IS MEASURED BY MOTION STARK EFFECT MAXIMAL VALUES OF β (β gt30) WERE OBTAINED WITH THE USE OF ldquoVORTEXrdquo CONFINEMENT METHOD Beklemishev AD Bagryansky PAChaschin MS and Soldatkina EI Fusion Science and Technology v57 4 p351 2010

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

• Slide 1
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
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• Slide 13
• Slide 14
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• Slide 30
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• Slide 33
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• Slide 39
• Slide 40
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• Slide 42
• Slide 43
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• Slide 46
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• Slide 48
• Slide 49
• Slide 50
• Slide 51
• Slide 52
• Slide 53
• Slide 54
• Slide 55
• Slide 56
• Slide 57
• Slide 58
• Slide 59
• Slide 60
• Slide 61

Time behavior of Te after switching on D0 neutral beams

t ms

Te

eV

0

50

100

150

200

250

4 45 5 55 6 65 7 75 8 8505 15 25 35 45

Thomson scattering measurements on the axis of GDT in the mid plane Ne = 3middot1013 cm-3 Sloshing ionsdensity in the turning points Nfast = 5middot1013cm-3

SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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SHIP EXPERIMENT (SINTESIZED HOT IONS PLASMOID) SHORT MIRROR TRAP (L = 30 cm) WAS INSTALLED BETWEEN GDT AND EXPANDER 1 MW TRANSVERSALNB INJECTION WAS ARRANGED (EBasymp 20 keV)

EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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EXCITATION OF ALFVEN ION CICLOTRON INSTABILITY DURING ACCUMULATION OF FAST ANISOTROPIC IONS IN COMPACT MIRROR CELL A=WWasymp35

UPPER TRACE IS ENERGY CONTENTOF FAST IONS BELOW ndashDEMOSTRATION OF THRESHHOLDOF AIC INSTABILITY

nT 1020m-3middotkeV

T s

nfast = 5middot1013cm-3

middotIT FOLLOWS FROM THE EXPERIMENT THAT AT PARAMETERS OF GDTNS THE INSTABILITY WILL NOT EXCITE AND THEBEHAVIOR OF FAST SLOSHING IONS WILL DESCRIBE BY CLASSIC COULOMB SCATTERING

GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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GDT-Important results

bull High-β (~ 06) MHD ndash stable plasma confinement is achieved in axially symmetric magnetic fieldbull Oblique injection of neutral beams at midplane

provides formation of fast ion density peaks near turning points

bull Electron temperature is determined by balance between energy transfer from fast ions and gas-dynamic losses through end mirrors

bull Relaxation rates of anisotropic fast ions are classical there are no microinstabilities

WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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WORKS ON NEUTRAL BEAM INJECTORS IN THE BUDKER

INSTITUTE OF NUCLEAR PHYSICS

DEVELOPMENT OF POWERFUL NEUTRAL BEAM INJECTORS IS AN IMPORTANT COMPONENT OF THE GDT NEUTRON SOURCE PROGRAM

bull FOCUSED BEAMS ARE REQUIRED BECAUSE OF SMALL DIAMETER OF PLASMA bull FINALLY HIGH POWER STEADY - STATE BEAMS ARE NEEDED

PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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PRESENT STATUS OF NB INJECTORS IN THE INSTITUTE

POWERFUL FOCUSED DIAGNOSTIC BEAMS ARE DEVELOPED FORMEASURING OF LOCAL VALUES OF Ne Ti β etc

PRESENT DAY PARAMETERS OF DIAGNOSTIC INJECTORS

ENERGY OF ATOMS (HYDROGEN DEUTERIUM) EB = 25 - 60 keVEQUIVALENT BEAM CURRENT IB UP TO 7 A

DURATION OF THE BEAM τB UP TO 1O SECONDS

PARAMETERS OF NEAREST FUTURE

FOCUSED DIAGNOSTIC INJECTOR FOR WENDELSTEIN ndash 7X EB = 65 keV

IB - UP TO 10 A DURATION OF THE BEAM τB UP TO 1000 SECONDS

COMISSIONING OF THIS INJECTOR IS IN PROGRESS

GEOGRAPHY OF NOVOSIBIRSK BEAMS

USA(2) GERMANY SWITSERLAND ITALY SPAIN RUSSIA

Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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Madrid Spain TJ-IIU 50 keV 4 A

Padua Italy RFX50 keV 4 A 50 ms

Lausanne TCV50 keV 3 A 2 s

Yuelich Germany TEXTOR55 keV 3 A 10 s

55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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55 keV 7 A 3 s diagnostic beam on Alcator C-Mod MIT USA

STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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STATIONARY AND QUASISTATIONARY FOCUSED NEUTRAL BEAMS

FOR PLASMA HEATING

-AT PRESENT THE MOST POWERFUL NB

INJECTOR FOR PLASMA HEATING IN THE

INSTITUTE HAS THE FOLLOWING PARA-

METERS EB = 40 keV IB=40 A τB =1 s

HOWEVER STORED EXPERIENCE AND

PRELIMINARY ANALYSIS ALLOWS ONE TO

STATE THAT A MODULE OF STATIONARY

FOCUSED NB INJECTOR WITH THE BEAM

ENERGY EB = 40 ndash 80 keV AND TOTAL

POWER P = 2 ndash 3 MW CAN BE BUILT

ALSO GOOD EXPERIENCE RELATED TO PRODUCTION OF NEGATIVE IONS HAS ACCUMULATED IN THE INSTITUTE ON THE GROUNDS OF THIS EXPERIENCE ONE CAN TELL ABOUT CONSTRUCTION OF 1 MeV 5 - 10 MW STATIONARY NEUTRAL BEAM MODULE

CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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CONCLUSIONS

bull THE PHENOMENA DISCOVERED AT GOL-3 (EFFICIENT PLASMA HEAT-ING BY REB SUPPRESSION OF ELECTRON THERMAL CONDUCTANCEBOUNCE INSTABILITY etc) MAKES MULTI-MIRROR REACTOR MORE REALISTIC bull DUE TO BOUNCE INSTABILITY EFFECTIVE ION MEAN FREE PATHDECREASES DOWN TO SINGLE MIRROR CELL SIZE THUS REACTOR WILL BE ABLE TO OPERATE WITH MORE RARE (OF ORDER OF3middot1015cm-3) PLASMA IT MEANS THAT COMPLETELY MAGNETIC CON-FINEMENT CAN BE USED bull SUPPRESSION OF LONGITUDINAL THERMAL CONDUCTION BY ANELECTRON BEAM CAN TURN OUT USEFUL FOR OTHER OPEN MAGNETIC SYSTEMSbull THE DATA OBTAINED IN THE GDT ARE SUFFICIENT TO DESIGN THENEUTRON SOURCE WITH POWER OF SEVERAL HUNDREDS kW AT THE SAME TIME THERE ARE NO PHYSICAL LIMITATION INHIBITING TO CREATION OF FULL SCALE NEUTRON SOURCE bull PROGRESS IN DEVELOPMENT OF SUPERCONDUCTING MAGNETS CAN LEAD TO SIGNIFICANT SIMPLIFICATION OF THE GDTNS DESIGN bull BESIDES THE GDT BASED FUSION REACTOR CAN TURN MOREREALISTIC

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