Fusion Neutronics, Nuclear Data, Design & Analyses - Overview of Recent FZK Activities -

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1 Forschungszentrum Karlsruhe Technik und Umwelt Fusion Neutronics, Nuclear Data, Design & Analyses - Overview of Recent FZK Activities - Ulrich Fischer Association FZK-Euratom Forschungszentrum Karlsruhe, Germany IEA International Workshop on Fusion Neutronics, Dresden, Germany, 5 September

2 Overview Nuclear Blanket Design Fusion power reactor & ITER Neutronics Research & Development MC sensitivity/uncertainty computational techniques Coupled MC/S N radiation field analysis for large systems CAD - Interface for MCNP Radiation damage simulation (BCA/MD/kMC) Nuclear Experiments & Analyses SiC transmission experiment (FNG) IFMIF Intense Neutron Source Neutronics, nuclear data, D-Li source term Validation analyses for transport & activation data 2

3 Blanket Design & Development EU Fusion Power Plant Conceptual Study (PPCS) Near-term concepts Helium - Cooled Pebble Bed (HCPB) blanket Water - Cooled Lithium Lithium-Lead (WCLL) blanket Advanced concepts Dual Coolant Lithium-Lead (DCLL) blanket Self - Cooled Lithium-Lead (SCLL) blanket with SiC/SiC structure 3d neutronic design analyses (TBR, power, shielding) ITER test blanket module HCPB test module design 3

4 PPCS Reactor Models WCLL SCLL 4

5 Shielding Performance: WCLL vs. HCPB WCLL total flux Neutron flux density (cm -2 s -1 ) HCPB fast flux WCLL fast flux PPCS central inboard module HCPB total flux Radial distance from FW (cm) 5

6 SiC transmission experiment (FNG) P1 P2 P3 P spectrometer neutron source 71.1 cm 6

7 SiC transmission experiment (FNG) 10-6 Neutron flux density [cm -2 sn -1 MeV -1 ] SiC P4 (58.42 cm) Measurement TUD EFF-3 FENDL-2 FENDL Neutron energy [MeV] 7

8 Sensitivities of neutron fluxes to Si and C data 1,0 1,0 0,5 SiC assembly detector P1 (12.70 cm) Si C SiC 0,5 0,0 SiC assembly detector P2 (27.94 cm) Si C SiC Sensitivity [%/%] 0,0-0,5-1,0 Sensitivity [%/%] -0,5-1,0-1,5-2,0-1,5-2,5-2, Neutron energy [MeV] -3, Neutron energy [MeV] 1,0 1,0 Sensitivity [%/%] 0,5 0,0-0,5-1,0-1,5-2,0-2,5-3,0-3,5-4,0 SiC assembly detector P3 (43.18 cm) Si C SiC Sensitivity [%/%] 0,5 0,0-0,5-1,0-1,5-2,0-2,5-3,0-3,5-4,0-4,5-5,0 SiC assembly detector P4 (58.42 cm) Si C SiC -4,5-5,5-5, Neutron energy [MeV] -6, Neutron energy [MeV] 8

9 Uncertainties of neutron fluxes at P4 Calculation uncertainties [%] Experiment Ex. + C. E [MeV] flux MC SiC Si C Calc. C/E (*) [%] Un. [%] E< E E E E E E E E E > E total 1.06E (*) EFF-3 Si and C EFF-2.4 data 9

10 SiC Transmission Experiment SiC transport experiment shows good quality of EFF Si data EFF-3 and EFF-2.4 Si data reproduce well fast (E>1 MeV) neutron flux when used with FENDL-2 C (JENDL-FF) data. Si-data: significant improvement over FENDL-1 & FENDL-2 FENDL-1: Gross underestimation of fast neutron flux (Si data) FENDL-2 tends to underestimate fast flux at deep penetrations C-data: FENDL-2 superior to EFF-2.4 EFF-2.4 C data (ENDF/B-VI): to be re-considered (inelastic scattering) Sensitivity to Si and C data Fast flux more sensitive to Si than to C cross-sections Calculated Uncertainties Dominated by inelastic scattering (Si, C) and absorption (Si) co-variances With few exceptions calculated uncertainties larger than experimental ones Total (experimental and calculated) uncertainty is in the range 5 to 12% 10

11 D(Li,xn) source function IFMIF Neutronics Reaction models & evaluated data files MCNP MC codes M c DeLi, M c DeLicious Thick lithium target experiments Data base development E 20 MeV INPE Obninsk /FZK co-operation Transport & activation data files (ENDF-6 format) Intermediate Energy Activation File IEAF-2001 Design of irradiation test modules High and medium flux test module (HFTM/MFTM) Data validation analyses IFMIF-like neutron spectrum (FZK & NPI Rez cyclotrons) Integral activation & transport experiments 11

12 IFMIF neutron flux spectrum ITER (first wall) HFTM (McDeLi) HFTM (McDeLicious) Neutron flux density [10 10 /cm 2 /MeV/s] ,01 0, Neutron energy [MeV]

13 D-Li forward neutron yield Forward Yield (Θ = 0 o ) Yield, /sr/µc MCNPX 10 1 McDeLi 10 0 McDeLicious - Daruga - Weaver - Goland - Amols - Nelson - Lone - Salmarsh - Johnson - Sugimoto Deuteron Energy [MeV] 13

14 D-Li thick target neutron yield spectra 10 0 Θ = 0 o Θ = 20 o 10-1 Spectral Neutron Yield, n/sr/mev/µc Sugimoto McDeLi McDelicious MCNPX 10-1 Θ = 60 o Neutron Energy [MeV] E d = 32 MeV Θ = 100 o Neutron Energy [MeV] 14

15 NPI Rez Neutron Transport Benchmark Neutron flux (20 o ) [10 8 n/sr/mev/µc] Experiment Bem et al. MCNP INPE/FZK data MCNP LANL-150 data Fe-slab (20 cm) Neutron energy [MeV] 15

16 ALARA/IEAF-2001 vs. FISPACT/EAF m 1h 1d 30d 1y 10y 100y 10 3 y Total Activity 10 4 y 10 5 y 10 6 y Fe Eurofer activation in Demo first wall Activity, Bq/kg H FISPACT/EAF-99: dashed with symbols ALARA/IEAF-2001: straight lines C 53 Mn Time after shutdown, hours 16

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