ITER: A Magnetically-Confined Burning Plasma Integrating ...
Transcript of ITER: A Magnetically-Confined Burning Plasma Integrating ...
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ITER: A Magnetically-Confined Burning Plasma Integrating Fusion Science and Technology
R.J. Hawryluk Deputy Director General
Director of the Department for Administration
2013 AAAS Annual Meeting Boston, MA
February 16, 2012
The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.
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ITER Will Study a Magnetically-Confined Plasma
Internal heating
Tritium replenishment
Li
Electricity Hydrogen
3.5 MeV 14 MeV
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Two Approaches to Fusion Development: Magnetic and Inertial Confinement
nested flux surfaces of a tokamak
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Existing experiments have achieved nTτ ~ 1×1021 m-3skeV and Gain = QDT ~ 1
JET and TFTR have produced DT fusion powers >10MW for ~1s ITER is designed to a scale which should yield QDT ≥ 10 at a fusion power of 400 – 500 MW for 300 – 500 s Progress has been determined by: - Scientific advances - Larger more powerful facilities
ITER
Gain =Q = Fusion PowerInput Power
~ niTi! E
Fusion Performance
ITER☼ ITER
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The ITER Agreement was Signed Nov. 21, 2006 China, Europe, India, Japan, Russia, South Korea, U.S.
• Over half the world’s population is represented in ITER. – A strong international scientific consensus that magnetic fusion can be
an important new non-CO2-emitting power source.
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• ITER is truly a dramatic step. For the first time the fusion fuel will be sustained at high temperature by the fusion reactions themselves. • MFE Today: 10 MW(th) for ~1 second with gain ~1 • ITER: 500 MW(th) for >300 seconds with gain >10
300 MW(th) for <3000 seconds with gain >5
• Many of the technologies used in ITER will be the same as those required in a power plant.
• Further science and technology development is needed to bridge the gap to commercialization.
ITER will Demonstrate the Scientific and Technological Feasibility of Fusion Power
Superconducting model Central Solenoid Coil
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Construction of Buildings and Civil Infrastructure by EU is Underway
PF Coil Winding Building
400kV Substation
Tokamak Complex Construction
ITER Headquarters Building
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Toroidal Field Coil
Central Solenoid!
Poloidal Field Coil
Vacuum Vessel
Cryostat
Divertor
ITER Components are Provided as Contributions from the Members
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TF Winding Pack
Toroidal Field Coil Status
Inner Leg Cross Section
TF coils split into 3 main production areas • TF conductors
- 450t of Nb3Sn (Europe, Russia, Japan, Korea, China and US) • TF structures
- 4500t of high precision stainless steel forgings and plates, assembled by welding in Japan
• TF windings and coils - 19 coils, 12T peak field, 20kV maximum voltage (Europe and Japan.)
EU JAPAN
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• Over ~80% of required 450t of Nb3Sn strand has been produced around the world
- Prior to ITER world production was 15 ton/year!
TF Strand Production Summary
TF Superconducting Strand Procurement is Largest in History
2009 2012
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TF Coil Structures Progress
B3 Segment
Manufacturability study of large TF coil components by Toshiba and its sub-contractor KHI
Inter-coil Structure - Forging
JA
Pictures courtesy JAEA & Contractors Toshiba & KHI
Prototype radial plate at CNIM
EU
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Central Solenoid Conductor Meeting ITER Specifications Has Been Qualified
• Three conductors by Furukawa, JASTEC and Oxford Superconducting Technology have been qualified as a CS conductor.
• Japan will provide the conductor and US will fabricate the coil.
JA US
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• VV sector and port PAs signed (EU, KO, IN, & RF) • EU- VV awarded to AMW (Ansaldo Nucleare S.p.A, Mangiarotti S.p.A
and Walter Tosto S.p.A) • KO - VV & port contract awarded to Hyundai Heavy Industries
Vacuum Vessel Status
• Vacuum Vessel is double-walled stainless steel – 19.4m outer diameter, 11.3m height, 5300 tonnes – provides primary tritium confinement barrier
EU, KO, IN, RF
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KO
The size, tight tolerances and large electromagnetic loads on the tokamak components are a challenge, - provides experience in developing the technology for a power plant.
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Negative Ion Neutral Beams are Under Development for ITER
Substantial extension of existing neutral beam technology Test facilities are under construction in Europe and India
A full-size mock-up bushing has been manufactured Voltage holding of -240 kV for 1 h has been demonstrated in the single-stage full-size mock-up bushing and 370kV over a two-stage mock-up.
1.56 m 0.29 m
EU, IN, JA
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n + 6Li → T + 4He + 4.8MeV n + 7Li → T + 4He + n - 2.47MeV
• Three dedicated stations for testing up to six tritium breeding concepts
Test Blanket Modules - Tritium Breeding
PbLi inlet
PbLi outlet
► Structures: Eurofer Steel ► Multiplier / Breeder: Pb-16Li (6Li 90%) ► Coolant: Helium at 8 MPa, 300/500°C
He-Cooled Lithium-Lead (HCLL) TBMs
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ITER Licensing Process Is Proceeding • In December 2010, the ITER safety files were formally accepted by
the French Authorities, which allowed the process of technical evaluation by the Nuclear Safety Regulator (ASN) to be launched as well as the public evaluation of the files organized by the local authorities.
• Public Enquiry was carried out in the period June – August 2011.
– A positive recommendation on the ITER Project was received on 19 September from the Inquiry Commission.
• The “Groupe Permanent,” a formal group of independent nuclear safety experts met on 30 November and 7 December 2011
• For the licensing process, a major milestone was achieved when French Prime Minister Jean-Marc Ayrault signed on 9 November 2012 the official decree that authorizes the IO to create the Installation nucléaire de base ITER;
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First High Power D-T Experiments Will Generate More Fusion Energy than All Previous
MFE Fusion Experiments Combined
• For comparison, JET produced 22 MJ per pulse ( 0.7 GJ total) and TFTR 7.5 MJ per pulse (1.7 GJ total) during their DT campaigns
• ITER will provide a unique facility to study the physics of magnetically confined burning plasmas
0
5
10
15
20
25
0
100
200
300
400
500
0 100 200 300 400 500 600 700t, s
Ip
Pfus
Paux
Q=10 scenario 250 GJ
Y. Gribov
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0.8 NBI ICRH
0.7
0.6
HDD–TT
0.5
0.4
0.3
0.2
0.1
00 0.1 0.2
ITERH–EPS97(y) (s)
th (s
)
0.3 0.4 0.5 0.6 0.7 0.8
JG98
.305
/2a
• τth ∝ <A>0.16±0.06
Cordey
The Energy Confinement Time Required by ITER is a Small Extrapolation from JET D-T Results
JET
H-mode scaling studies provide a good technical basis for baseline operation of burning plasma experiments. ITER will enable a definitive test of confinement.
ASDEXAUG
C-MODDIII-D
JETJFT-2MJT60-UPBX-M
PDX
10.001.000.100.01τE,th [s]IPB98(y,2)
0.01
10.00
1.00
τ E,th
[s]
0.10
ITER
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Energetic Alpha-particles Were Well Confined in Normal Shear Discharges
3.5 3.02.52.01.51.00.50.0 0.70.60.50.40.30.20.10.0
Minor Radius (r/a)
Data TRANSP:
D!=0 (w/error band)
D!=0.03 m2/s
Inte
nsity
(101
0 ph
/s-c
m2 -
ster
)
Plasma Surface
Neutral Beam
Charge exchange between fast beam neutrals and nonthermal alphas
DetectOptical Emission
E! = 0.15-0.6 MeV DHe / !D ~ 1
0
5
10
15
20
25
0 0.2 0.4 0.6 0.8 1
Hel
ium
Den
sity
(x10
16 m
-3)
r/a
No Transport
DHe, VHe from gas puffData
4.75 s
Consistent with "pHe/"E = 8, acceptable for a reactor
*
Alpha particles were well confined.! 0 ≤Dα≤ 0.03 m2/s!!
He ash from the slowing down alphas transported from the core to the edge in supershots. (DHe/χD ~ 1)!! E. Synakowski
ITER will extend these results especially ash buildup.
TFTR!
R. Fonck, G. McKee, B. Stratton
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Initial Evidence of Alpha-particle Heating on TFTR and JET
• Alpha heating ~15% of power through electron channel.
• "Palpha/Pheat ~12%!!- !30-40% through the !
!electron channel""• Comprehensive study of alpha heating requires higher values of
Palpha/Pheat .
T e(R
) (ke
V)
Major Radius (m)2.6 2.8 3.0 3.2
1
0
0.5
0
5
10
T e(D
T) -
T e(D
) (ke
V)
D Only(17 Plasmas)
D-T, Pfus ≈ 5 MW(6 Plasmas)
Measurement
TRANSP Prediction
G. Taylor, J. Strachan
T e(D
T) -
T e(D
) (ke
V)
T e
(R)
(keV
)
P. Thomas, et al.
TFTR!
T e(R
) (k
eV)
T e(R
) (k
eV)
T e(R
) (k
eV)
ΔT e
(0)
(keV
)
Pα (MW)
JET
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Alpha Particle Driven Instabilities Were Stable in TFTR and JET Normal Shear D-T Discharges
• As alphas slow down they can interact with Alfvénic instabilities in plasma – Valpha ~ Valfvén
• Some global Alfvén waves (TAE) are very weakly damped
• Fusion alphas interact with them more than the thermal plasma
• Alpha particle drives the
waves depending upon gradients in alpha distribution at resonance
Input Power (MW)1 10 205
10-8
10-7
10-6
10-5
10-9
Mod
e A
mpl
itude
[B!/B
0]~
0.01
0.10
1.00
10.00
100.0
Loss
Fra
ctio
n (%
)
- NBI driven TAE
- ICRF driven TAE
D-T experiments
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TFTR Alpha-particle Physics Studies in Reversed Shear Discharges Resulted in New Discoveries.
2.00
PNBI(MW)
TIME(s)NBI off
!"(0)0
Neutral Beam Injection
10-3
3x10-2
2.5TIME(s)
3.0
BB~
n=4
n=5n=3
n=2
2.8 2.9 3.00
6 x10-9
0
25
103101
!(0)
“Damping”
“Drive”
“Response”
wall
T
• Alpha-driven TAE (subsequently identified as Cascade Modes) were observed.
• Sensitive to the q-profile and damping mechanisms.
• ITER will study the role of alpha-driven instabilities in both the high QDT and steady state operating regimes
• PPPL/IFS quasilinear model predicts that alpha particle losses are acceptable in high QDT operating regimes • Further work required to assess
steady state operating regimes. R. Nazikian, Z. Chang, G. Fu ,
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ITER will Provide a Power Plant Scale Test of the Extraction of Heat from an MFE Fusion Plasma
• Long pulse, high heat flux operation can result in erosion or local damage.
– Nine years of JET operation has a comparable ion fluence to the divertor as~3 high power DT shots on ITER.
– Where will the sputtered material migrate to? – Development of high recycling divertor, Edge Localized
Modes and Disruption Mitigation are critical issues. • Dust has not been an issue in current experiments but there
will be safety restrictions on ITER • Tritium retention in graphite based on JET and TFTR
experiments would be a serious concern. – TFTR tiles 16% retention – JET 12% retention
• Results from JET with tungsten divertor for reduced tritium retention are very encouraging.
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MFE has Entered the Fusion Plasma Regime and ITER will Test Performance at Power Plant Scale • MFE has studied DT fusion plasmas with a Gain ~ 1 and
fusion energy of 22 MJ per pulse
• Detailed results from a broad international program have provided a solid basis for predicting ITER fusion performance
• An international R&D Program has extended technology to provide a strong scientific and technology basis for constructing ITER
• ITER and the associated International Magnetic Fusion Program are on track to:
– Produce fusion power of 500 MW at a Gain of 10 for 300-500s at the physical size of a power plant
– Demonstrate the technological feasibility of fusion power
• Full potential and consequences of alpha heating will be explored on ITER!