MEGAPIE – A liquid Pb-Bi target at SINQ · 2003-09-15 · Paul Scherrer Institut • 5232...

Paul Scherrer Institut • 5232 Villigen PSI BNL-Ronkonkoma/WS on High-Power Targetry, 9.2003 /GF34

Workshop on High-Power Targetry for Future Accelerators

Ronkonkoma, 8.-12.9.2003

MEGAPIE –A liquid Pb-Bi target at SINQ

F. Groeschel Paul Scherrer InstitutVilligen, Switzerland

on behalf of the MEGAPIE Team

MEGAPIE-TEST

Departmentof Energy


5th Framework Program

TRANSMUTATION (6.5 MEuro)Basic Studies:

MUSEHINDAS

N-TOF_ND_ADS

TRANSMUTATION (7.2 MEuro)Technological Support:

SPIRETECLA

MEGAPIE - TEST

PARTITIONING (5 MEuro)PYROREPPARTNEWCALIXPART

TRANSMUTATION (3.9 MEuro)Fuels:

CONFIRMTHORIUM CYCLE

FUTURE

TRANSMUTATION (6 MEuro)Preliminary Design Studiesfor an Experimental ADS:

PDS-XADS

Projects on ADvanced Options for Partitioning and Transmutation (ADOPTADOPT)


MEGAPIE ObjectivesAn experiment to be carried out in the SINQ target location to demonstrate the safe operation of a liquid metal spallation target of about 1 MW beam powerThe minimum design service life will be 1 year (6000 mAh).

�Demonstration of feasibility forfuture ADS development

�Increase neutron flux for SINQ


Contents� Objectives� SINQ� MEGAPIE Target� Nuclear Assessment� Thermal hydraulics� Radiation Damage� Heat Removal� Handling of Radiactive Products� Safety� Status and Conclusions


590 MeV, 1.8 mACW proton accelerator

575 MeV, 1.25 mA spallation neutron source


SINQ Spallation Neutron Source


SINQ Target Mark II/III

� 150 rods (Ø 10.7 mm, 170 mm long)� 316L stainless steel tubes filled with Lead� about 20 rods for STIP program filled with miniature specimens of different materials (F/M steels, austenitic, W, Ta, SiC/SiC, Hg or LBDE capsules)� Temperature range up to 250C (STIP-1), up to 350C (STIP2), 450C (STIP-3), � 650C (STIP-4)� Irradiation period is 2 years (peak fluence of 20 dpa)


SINQ Target

970

Highest hook positionin exchange flask

950

32

Exchange flaskpositioning base

max420

570,5

440

403

212 2110,5

4394

4996,5

10386,5

219 550,5

Top of proton beam collimator

Exchange flask gate valve

Targettransportsleeve

Bottom of target storage pit

SINQ targetmain dimensionsand clearancesto surroundings

MP_basic conceot.ppt


SINQ and Target

SINQ Target Block

MARK-II

ZT1

ZR2ZR1

ZT3ZT2

ZR4

D2

B1A

C

ZR3

4

3F

E

G

ZR5

8

J 6

I

5

H

K

7

9

L

10

M

Solid Target


Proton Beam ProfileNormal Operation, Target E 4 cm

U. Rohrer/PSI

σx = 2.1 cm, σy = 3.78 cm

I max 20.7 µA/cm2 per 1 mA

Accelerator Proton Beam in 2005: 2.0 mABeam on SINQ: 1.4 mA at 575 MeV


Reasons for LBE• No Radiation Damage• Good Heat Removal• Low Melting Point• Low thermal neutron cross section• Low activation of cooling water

• Corrosion• Po production (α)• Complex Handling• Limitation Beam

Window

0.110.0340.17389barnTermal Neutron Cross Section

0.150.150.140.12J/gKSpecific Heat

167015601740356.6oCBoiling Point

125271.3337.5-38.9oCMeltimg Point

-1.48-3.353.32-%Solidification Shrinkage ∆V

1.752.916.110-5K-1Lin. Thermal Expansion

10.5710.0710.713.55liquid

10.739.7511.35-g/cm3Density (20oC)

208.2209207.2200.6g/molMass

„82.5“838280Atomic Number

LBEBiPbHgProperties


MEGAPIE Target

Beam energy: 575 MeVBeam current: 1.74 mA (design)Target material: Lead-bismuth

eutecticLBE volume: 85 lWetted surface: 8 m2

Deposited Heat: 650-700 kWLBE T range: 230-380°C Max. flow velocity: ~1.2 m/sBeam window: T91 martensitic steelWindow Temperature: 330-380°C Radiation Damage: 20 dpaOther components: 316L

Target Shielding

Main EMP Flowmeter

Bypass EMP Flowmeter

Upper Target Enclosure

Main Guide Tube

Bypass FlowGuide Tube

Expansion Tank

12 Pin Heat Exchanger

Central Rod Heaters and Neutron Detectors

T91 Lower Liquid Metal Container

Target Head Feedthroughs

LBE Leak Detector

Lower Target Enclosure


Nuclear Assessment

� Code comparison calculations� MCNPX and FLUKA� Validation experiments (CERN, PSI, HINDAS) on gas and spallation products production� Instrumentation of target with microfission chambers and activation foils� Neutron flux measurement at beam ports


MEGAPIE Neutron Flux

Performance comparison for different target materials under SINQ conditions(calculations with the code LAHET)

0

0.5

1

1.5

2

2.5

0 10 20 30 40 50 60 70 80 90 100radial position [cm]

ther

mal

flux

[rel

. uni

ts]

Zr rodsPb + steel cladding (0.5 mm)Pb + Zr cladding (0.7 mm)Pb-Bi

targ

et re

gion

beam

tube

s

cold

so

urce

LAHET calculations A. Dementjev, E. Lehmann

Peak flux1.8-2 E14 total neutrons1.2-1.3E14 thermal neutronsat 1.74 mA

Increase of >40% compared to current solid lead target


Neutron Yield

Neutrons per Proton

- 1.23-0.248Container8.496.17Net

- 0.401- 0.044D2O- 0.635- 1.01Cladding- 0.232- 0.113Target Int.10.997.62TotalLBEPb/steel

E. Pitcher et al.: Icans-XVI, 2003


Nuclear Assessment

E. Pitcher, 2002

-30

-20

-10

0

10

20

30

40

50

5 10 15 20 25 30 35 40 45 50

200

400

600

800

1000

1200

1400

x 10 11

r (cm)

z (c

m)

Thermal Neutron FluxE<0.625 eV

1.4 1014

-30

-20

-10

0

10

20

30

40

50

5 10 15 20 25 30 35 40 45 50

10 10

10 11

10 12

10 13

10 14

r (cm)

z (c

m)

Proton Flux, 1.74 mA

1014


Beam Window: T91 martensitic 9Cr-1MoVNb steel

� Removal of Heat (5kW): cold LBE jet across window�CFD modelling�Experimental verification (KILOPIE, TECLA)

� Static and Fatigue Loads (ABAQUS, ANSYS, RCC-MR)� Corrosion and LME (TECLA)� Radiation Damage (SPIRE, STIP)


Lower Liquid Metal Container

LBE ContainerBeam Entrance WindowCarry LBE Leak Detector

4 mm outside2 mm in spallation zone1.5 - 2 mm in window

T91

Reference Design


Thermalhydraulics – CFD simulations

0

100

200

300

400

500

600

700

800

900

1000

0 0.05 0.1 0.15 0.2 0.25 0.3 0.35

Height [m]

Hea

t Dep

ositi

on [M

W/m

**3]

CFX-4.3

FLUKA

722.4719.6Total6.035.55Guide tube

1.212.68T91 Hull5.285.56Window

709.9705.8LBE

CFX-4.3 [kW]

FLUKA [kW]

Material

342.5355.7339.4384.4= Bypass1.4 mA

360.3389.5363.1424.1⊥ Bypass

370.2386.8368.2422.7= Bypass1.74 mA

WindowC. RodGuide T.LBEMaj. AxisBeam

Tpeak [C]

T. Dury, PSI, 20031.74 mA


Power Deposition in Beam Windows

0 2 4 6 80

100

200

300

400

500

600

Scattered beam

AlMg3OuterL D2OCoolant AlMg3InnerL T91LMC

Pow

er d

epos

ition

[W/c

m3/

mA]

Radial Distance X [cm]

4.6 kW/mA

2.2 kW/mA

Y. Foucher, PSI Report 2002

Normal Operation Target E 4 cm Baseline Profile


Beam Window Cooling

Baseline Beam Profile, 1.74 mABypass Jet Flow: 0.25 l/s Annular Down Flow: 3.75 l/s

Y. Dury: PSI Report 2002, Annex


Experimental Validation

15 Qmain/Qbypass 10

HYTAS Water Experiment, FZKLBE Heated Jet Experiment, FZKLBE KILOPIE Experiment, PSI-FZK


Stress Analysis

55 MPa

63 MPa

A. Zucchini, ENEA


Fatigue Resistance of T91 –Influence of LBE

Design curve acc. RCC-MR Kalkhof, Grosse: IWSTM-5, 2002


Radiation Damage

0 2 4 6 80

3

6

9

12

15

T91 Liquid Metal Container200 days at 1 mA

Neutrons Protons Totaldamage

Dam

age

[dpa

]

Radial Distance X [cm]0 2 4 6 8

0

1

2

3

4

5

6

AlMg3 Outer Enclosure200 days at 1 mA

Neutron Proton Totaldamage

Dam

age

[dpa

]

Radial Distance X [cm]

0 5 10 15 20 25 300.0

0.4

0.8

1.2

1.6

2.0

Cylindrical Target Section200 days at 1 mA

TotalLMC TotalAlMg3e TotalAlMg3i

Dam

age

[dpa

]

Axial Distance [cm] Y. Foucher, 2002


Radiation Damage

Dai et al.: PSI Annual Report 2001


Radiation Damage and He Production

Henry, Jung: IWSTM-5, 2002


Radiation Effect on Impact ToughnessInner surface temperature

1.4 mA

340.0333.1326.3319.4312.6305.7298.9292.0285.1278.3271.4264.6257.7250.9244.0

Jet flow

292°C299°C

306°C

~315°C~315°C

10107.97.9

5.75.7

1111278°C278°C

207°C207°C135°C135°C

311°C311°C

Inner surface temperature

1.4 mA

340.0333.1326.3319.4312.6305.7298.9292.0285.1278.3271.4264.6257.7250.9244.0

Jet flow

292°C299°C

306°C

~315°C~315°C

292°C299°C

306°C

~315°C~315°C

10107.97.9

5.75.7

1111278°C278°C

207°C207°C135°C135°C

311°C311°C

0 100 200 300 400 500 600

0

100

200

300

400 HT-9, nfast, 13/26 dpa HT-9, nmixed, 4-40 dpa, MANET-I, nmixed, 4-13 dpa DIN 1.4914, nmixed, 1-2 dpa T91, nmixed, 4-40 dpa

Shift

of D

BTT

(°C

)

Irradiation Temperature (°C)

-100 -50 0 50 100 150 200 2500

2

4

6

8

10T91

Dose He DBTT (dpa) (appm) (°C)

0.0 0.0 -54 4.6 265 54 6.8 450 165

Abso

rbed

Ene

rgy

(J)

Temperature (°C)

0 100 200 300 400 500 600 700 8000

20

40

60

80

100

120

140

∆DBT

T CV

N (°

C)

SP

∆DBT

T SP (°

C)

Helium concentration (appm)

0

50

100

150

200

250

300

350

Ti<=275°C CVN F82H T91 Optimax Optifer-V


LiSoRLiSoR in in irradiation facility irradiation facility IP1IP1

Beam energy-72MeVMax current-30 µAMax proton flux- 2x1014 p/cm2/sBeam time per test up to 10daysRadiation damage- ~ 0.25


LISOR – 1st Experiment

230

240

250

260

270

280

290

300

310te

mpe

ratu

re/°

C

1'500 2'000 2'500 3'000 3'500 4'000time / min

test section inlettest section outletthermocouple

beam on beam off


Heat Removal

� Forced flow by in-line electromagnetic pump (4 l/s) � Bypass-flow by in-line EMP (0.25-0.35 l/s)� 12 pin heat exchanger� Diphyl THT intermediate cooling loop

3-way valve and HEX bypass to control LBE THX outlet temperature

� Intermediate water cooling loop


LBE Flow Rates and Temperatures

L

F

F

Beam Window380°C outside

330°C inside

Downcomer3.75 l/s, 0.33

m/s230-240°C

Nozzle 1.2 m/sBeam Window 1 m/s

Guide Tube4 l/s, 0.33 m/s

380°C

Bypass Pump0.25 l/s, 0.2 m/s

230°C

Heat Exchanger4 l/s, 0.33 l/s/pin

0.46 m/sLBE 380-230°C

Main Pump4 l/s, 1.2 m/s

380°C

Heat Exchanger (Oil)10 i/s, 5.5 m/s

140-175°C inside

Bypass Tube0.25 l/s, 1m/s

230-240°C


EM Pump - System

IPUL: Design Report, 2002


Target Heat Exchanger� Heat Removal� Thermal Transients

150

170

190

210

230

250

270

290

310

330

350

0 5 10 15 20 25 30 35

Temps (s)

Term

péra

ture

(°C

)

0

1000

2000

3000

4000

5000

6000

7000

8000

9000

10000

h (W

/m2K

)T (°C) PbBi

T (°C) Diphyl

h PbBi

h Diphyl

10 s

Stresses remain below 110 MPa limit

according to RCC-MR


Heat Removal System

626 kPaTHT P drop12 mPump Head

3.5 m/sTHT Velocity9.28 kg/sFlow Rate

59 C130 C230 COutlet

40 C165 C330 CInlet

H2O IHXTHT IHXLBE THX

Ansaldo NucleareRelap5 CalculationBeam trip 10 s+20 s ramp


Handling of Spallation Products

� Safe enclosure� Drain or freeze ?� Behaviour of Po� Release of Volatiles


Spallation Products

Totale AktivitätZircaloy-Target

Totale AktivitätPb-Target

α - Aktivität PbBi-TargetPbBiLeistung Zircaloy-Targetbei AbschaltungLeistung Pb-Target bei Abschaltung

NachwärmeleistungZircaloy-Target

Nachwärme-leistung

PbBi-Target

Nachwärme-leistung

Pb-Target

α - Aktivität Pb-Target

Totale AktivitätPbBi-Target

Abkühlung einesTargets nach 1 JahrBestrahlung mit 1mAProtonenstrahl

1Tag 5Tage 2Wo 4Wo 3Monate 1Jahr 3Jahre 10Jahre 30Jahre

Abkühlzeit

1011

1012

1013

1014

10151015

1011

1012

1013

1014

10'000

1000

100

10

1

Nac

hwär

mel

eist

ung

(W)

Tota

le α

-Akt

ivitä

t [Bq

]

Tota

le A

ktiv

ität [

Bq]

(β +

γ +

α)

3.08Os0.055Zn1.03Ir

0.137Xe0.274Cd3.50Pt0.205Kr0.274Sn2.53Au0.001Ar0.137Te11.78Hg0.479He0.048J4.59Tl

0.548H0.027Cs1.17Po

F. Atchison, SINQ/816/AFN-702

Production (g) in a LBE target after 1 yea, 6000 mAh


Handling of Gases

� Safe enclosure� Periodic venting in decay tank (shielding)� Filters for volatiles (active carbon + HEPA particle filters)� Gas sampling


Gas Production and Handling

Production (Liter NTP)After 1 year and 6000 mAh

6.3 ... 8.7Total0.024Xe0.06Kr

0.0026Ar0.24 .. 2.6He

6.0H

Enderle: Neutronic Benchmark

AnsaldoReference Design


Target Head and Top Shielding

Target SupportFeedthrough for Supplies and InstrumentationShielding


Barrier Concept - Containment of Radioactivity

Internal effects

• Leak/Break of Liquid Metal Container� Guillotine break of LMC� Leak or Jet of LBE� Water/Oil Leak

• Leak in Gas System3 barriers for gas systems

4 barriers for liquid metal

External effects

• Focused Beam• Earthquake• Airplane Crash• Fire


Failure of 1st Containment

Target with second enclosureAr/He insulation gas <0.5 bar LBE leak detector LBE level detectors

Second containment for ancillary systems with radioactive inventory He puffer gas < 0.9 bar Continuous monitoring

catcher


Summary and Conclusions� Design of main components completed� Optimisation and validation ongoing� Licensing Process ongoing� Target manufacturing started� Input from Design Support on

� Thermohydraulics/Thermomechanics of transients� LM - Speciation and volatility of spallation products� Materials – Corrosion, LME and radiation damage� Reliability assessment

� Target on the Critical Path Delivery in June 2004Intensive testing in 2004� Irradiation in 2005

MEGAPIE – A liquid Pb-Bi target at SINQ · 2003-09-15 · Paul Scherrer Institut • 5232...

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Transcript of MEGAPIE – A liquid Pb-Bi target at SINQ · 2003-09-15 · Paul Scherrer Institut • 5232...