1858-3 school on physics, technology and applications of...
TRANSCRIPT
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1858-3
School on Physics, Technology and Applications of Accelerator DrivenSystems (ADS)
Didier DE BRUYN
19 - 30 November 2007
Myrrha Project CoordinatorNuclear Research Division
SCK CENBE-2400 Mol (Belgium)
Engineering Design of the MYRRHA.Part III
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Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MYRRHA – Draft 2Sub-critical Core Neutronics Design
Calculations
E. Malambu & H. Aït Abderrahim
On behalf of MYRRHA team and MYRRHA support
http://www.sckcen.be/myrrha
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2Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Contents
1. Core configuration
2. Computational tools (Nuclear data and Codes)
3. Geometrical model features
4. Neutronics static parameters and characteristics
5. Induced damage in structural material
6. MA and LLFP Transmutation performance assessment
7. Reactivity effects and Operational sub-criticality margins
8. Concluding remarks
9. Driving proton beam: 350 MeV-5 mA Vs. 600 MeV-2 mA
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3Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Sub-critical core design requirements and constraints
Proton Beam:
350 MeV-5 mA
Spot size (FWHM)=15 mm (gaussian spatial shape assumed)
The initial keff ~ 0.95
Nominal power ~50 MWth
Fast neutron flux: ~ 1015 n/cm²s
Thermal neutron flux (inside IPS-like loop): 1.0 – 2.0 1015 n/cm²s
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4Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MYRRHA ADS:Typical Core Configuration
102 channels Target-block hole fitted out within the 3 central channelsSurrounding active zone loaded with 45 fuel SA (30wt% Pu/HM; 91 pins/SA)Outer reflector zone composed of 54 “reflector” assemblies
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5Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Core Analysis tools
Nuclear data (within table range; INC-model beyond): Neutrons: JEF2.2 (MCB-package) combined to LA150n(Pb, Bi and steel elements);
LA150h or physical models for protons.
MCNPX 2.5.e beta version used:
Enables one to “mix-and-match” data tables having different upper energy boundaries and table data with INC models
ALEPH (home-made)code, coupling MCNPX and ORIGEN2.2 in a more efficient way, to carry out core burn-up calculations
Nuclear data: JEF2.2 processed using NJOY99.90
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6Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Geometrical model
Updated and Completed
Fuel pin and assembly design revisedAssembly extension parts from the inlet nozzle through the outlet nozzleAssembly and fuel-pin bundle gridsCore barrel and core suspension tubeTop lid and radial shielding concrete Top (pool) gas plenumSpallation target loop (inner part)
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7Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MYRRHA MODEL for MCNPX calculations
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8Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MYRRHA MODEL for MCNPX calculations (cont’d)
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9Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MYRRHA: general sketch
Emergencyheat exchangers
Interim fuelstorageHX-pump group
(2 HXs - 1 pump)
Spallation loop
Core
Fuel handlingmachine
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10Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Results
Comprehensive and reliableset of results provided:
Reactivity effects Nuclear data sensitivity analysisOperational sub-criticality marginsConsistent Power and Flux mapsIrradiation-induced damage parameters (DPA, gas-production)MA and LLFP transmutation performances
Improved quality of document
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11Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Overview of the MYRRHA core characteristics (BOL)
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12Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Sub-critical Core:Assembly Power map
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13Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Spallation target Heating
kW/cm3
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14Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Pin-by-pin power map (hot assembly) and
linear power density curve (hot pin)
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15Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Spectra and Flux
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16Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
DPA-damage and Helium-gas production in T-91steel pipe
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17Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MA and LLFP transmutation:Core loading
MA pellet vector
Pu/Am/Cm/Mg/O238Pu/239Pu/240Pu/241Pu/242Pu241Am/243Am 66.67/33.33
23.25/30.32/6.06/19.18/20.195.06/37.91/30.31/13.21/13.51
244Cm/245Cm 90/10
wt% fraction
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18Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Neutron spectra in MA and LLFP samples
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19Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
MA and LLFP (amounts in gram)
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20Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Core configuration with IPS-like water-moderated loop
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21Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Ks swing
∆ρ=-1667 pcm pcm/cycle (1cycle=90 EFPDs) (i.e., -19 pcm/EFPD).
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22Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Fuel burn up after 90 EFPDs in MWd/kgHM)
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23Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Assembly relative power at BOC and at EOC
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24Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Fuel Assembly reactivity worth map
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25Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Fuel Temperature (Doppler) effect Doppler constant (KD = Tdk/dT)
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26Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Fuel Temperature (Doppler effect) Doppler coefficient (dk/dT)
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27Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Coolant Temperature (density) reactivity effect (dk/dT)
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28Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Sensitivity to neutron cross-section libraries
err errmax errint Ptable ks keff ∆ρ φ*JEF 2.2 0.002 0.04 5.0E-7 yes 0.95961 0.95506 496 1.12
0.002 0.04 5.0E-7 no 0.95979 0.95578 437 1.10ENDF 6.8 0.002 0.04 5.0E-7 yes 0.96881 0.95895 1061 1.33
0.001 yes 0.96470 0.95479 1076 1.290.001 0.01 5.0E-8 yes 0.96423 0.95435 1074 1.29
JEF 2.2 0.001 0.01 5.0E-8 no 0.96457 0.95568 964 1.260.002 0.02 1.0E-7 yes 0.96437 0.95509 1008 1.270.002 0.04 5.0E-7 yes 0.96464 0.95480 1068 1.29
ENDF 6.8 0.001 0.01 5.0E-8 yes 0.96898 0.95971 997 1.31JEFF 3.0 0.001 0.01 5.0E-8 yes 0.96511 0.95533 1061 1.29
Optimal accuracy
Nuclear data
SCK
•CE
NM
CB
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29Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Estimated operational sub-criticality margins
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30Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Concluding remarks
The sub-critical core achieves a primary source neutron multiplication factor, ks, of 0.9600 (the keff-eigenvalue being 0.9552). The adopted sub-criticality level, -4686 pcm, is larger enough to keep the MYRRHA core far away from criticality.
The reactivity swing induced by core burn-up amounts to about -19 pcm/EFPD starting from a fresh core
At 5 mA beam intensity, the sub-critical core delivers a thermal power of 51.75 MW. An additional 1.43 MW is deposited by the proton beam mainly inside the liquid metal spallation target.
The average linear power density over the hottest pin is 272 W/cm with the peak power limited to 352 W/cm.
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31Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Concluding remarks
The targeted order of magnitude in fast flux, viz. 1015
n/cm2s, is achieved in the near of the hottest fuel pin.
An accumulated dpa-damage dose up to 39 dpa over a 3x90 EFPDs irradiation period may be expected along the spallation target pipe with appm(He)-to-dpa ratios up to 8.
MA transmutation has been investigated by considering six IMF-target assemblies, containing 7.24 kg of low graded plutonium, 9.04 kg of americium and 1.81 kg of curium, irradiated in fast spectrum channels during a 3-years campaign (810 EFPDs in total). The calculations yield a net decrease of 2.48 kg in the actinide mass, mainly due to the removal of americium (-2.46 kg). There is net mass increase of 0.46 kg for curium. The burned-out mass of plutonium is 0.51 kg
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32Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Effect of proton beam spatial shape
00.010.020.030.040.050.060.070.080.090.1
0 10 20 30
r (mm)
y no
rmal
ised
Gaussian spatial beam profile
Real Beam Profile
kS 0.9601 0.9597M 25.04 24.82n/p 6 6
P (MW) 51.75 50.9 1E+14
1E+15
1E+16
-35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35
x-axis distance from the core centerline (cm)
Neu
tron
flux
(n/c
m2 s)
Total fluxFast flux (E>0.75MeV)
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33Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Proton beam option:350 MeV-5 mA Vs. 600 MeV-2 mA
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34Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
350 MeV-5 mA Vs. 600 MeV-2 mA: Fast flux
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35Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
350 MeV-5 mA Vs. 600 MeV-2 mA: Fast flux
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36Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
350 MeV-5 mA Vs. 600 MeV-2 mA: Linear power density along the hottest pin
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37Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
350 MeV-5 mA Vs. 600 MeV-2 mA: DPA/270EFPDs along the target duct
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38Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
350 MeV-5 mA Vs. 600 MeV-2 mA: DPA/270EFPDs along the hottest pin clad
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39Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Non-fission (external) neutron source distribution
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40Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Proton particle distribution
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41Presented at the Workshop on “Technology and Applications of Accelerator Driven Systems” Trieste, 17-28 October 2005
Concluding remarks
• A 600 MeV-2 mA driving proton beam is shown to yield similar core characteristics as a 350 MeV-5mA proton beam
• In the case of 600 MeV the flux and hottest fuel pin power are less peaked and the peak dpa-damage is also lower.
• Moreover the target heating rate inside the liquid-metal spallation target is lower by a factor of two.
• Calculations show that neither neutrons nor protons will reach the bottom of the tank. No specific shielding is therefore required.