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 2002 1
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
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
PPCS Reactor Models WCLL SCLL 4
Shielding Performance: WCLL vs. HCPB WCLL total flux 10 15 Neutron flux density (cm -2 s -1 ) 10 14 10 13 10 12 HCPB fast flux WCLL fast flux PPCS central inboard module HCPB total flux 10 11 0 50 100 Radial distance from FW (cm) 5
SiC transmission experiment (FNG) P1 P2 P3 P4 43.18 12.70 27.94 58.42 spectrometer neutron source 71.1 cm 6
SiC transmission experiment (FNG) 10-6 Neutron flux density [cm -2 sn -1 MeV -1 ] 10-7 10-8 SiC P4 (58.42 cm) Measurement TUD EFF-3 FENDL-2 FENDL-1 10-9 10 0 10 1 Neutron energy [MeV] 7
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 [%/%] -0,5-1,0-1,5-2,0-1,5-2,5-2,0 2 4 6 8 10 12 14 Neutron energy [MeV] -3,0 2 4 6 8 10 12 14 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 -4,5-5,5-5,0 2 4 6 8 10 12 14 Neutron energy [MeV] -6,0 2 4 6 8 10 12 14 Neutron energy [MeV] 8
Uncertainties of neutron fluxes at P4 Calculation uncertainties [%] Experiment Ex. + C. E [MeV] flux MC SiC Si C Calc. C/E (*) [%] Un. [%] E<0.1 8.67E-06 0.96 1.62 1.28 0.99 1.88 0.5 6.65E-07 0.6 2.87 1.96 2.09 2.93 1 3.37E-07 0.6 3.29 2.24 2.41 3.34 2.5 4.19E-07 0.32 4.02 2.76 2.92 4.03 0.99 3.70 5.48 5 1.74E-07 0.41 5.37 3.88 3.71 5.39 1.03 3.70 6.54 7.5 8.86E-08 0.33 6.55 4.69 4.57 6.56 1.25 5.07 8.29 10 5.34E-08 0.39 8.44 5.71 6.21 8.45 1.17 5.07 9.85 12.5 4.55E-08 0.34 12.2 8.09 9.13 12.2 0 1.07 3.33 12.65 E >12.5 1.11E-07 0.14 12.29 7.54 9.7 12.2 9 1.08 3.33 12.73 total 1.06E-05 0.79 1.62 1.27 1.01 1.80 (*) EFF-3 Si and C EFF-2.4 data 9
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
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
IFMIF neutron flux spectrum 10 6 10 5 ITER (first wall) HFTM (McDeLi) HFTM (McDeLicious) 10 6 10 5 Neutron flux density [10 10 /cm 2 /MeV/s] 10 4 10 3 10 2 10 1 10 0 10 4 10 3 10 2 10 1 10 0 10-1 0,01 0,1 1 10 100 Neutron energy [MeV] 10-1 12
D-Li forward neutron yield Forward Yield (Θ = 0 o ) Yield, 10 10 /sr/µc MCNPX 10 1 McDeLi 10 0 McDeLicious - Daruga - Weaver - Goland - Amols - Nelson - Lone - Salmarsh - Johnson - Sugimoto 10-1 0 10 20 30 40 Deuteron Energy [MeV] 13
D-Li thick target neutron yield spectra 10 0 Θ = 0 o Θ = 20 o 10-1 Spectral Neutron Yield, 10 10 n/sr/mev/µc 10-2 10-3 10-4 10-2 10-3 10-4 Sugimoto McDeLi McDelicious MCNPX 10-1 Θ = 60 o 10-5 0 10 20 30 40 Neutron Energy [MeV] E d = 32 MeV Θ = 100 o 0 10 20 30 40 50 Neutron Energy [MeV] 14
NPI Rez Neutron Transport Benchmark Neutron flux (20 o ) [10 8 n/sr/mev/µc] 10-1 10-2 10-3 Experiment Bem et al. MCNP INPE/FZK data MCNP LANL-150 data Fe-slab (20 cm) 0 5 10 15 20 25 30 35 Neutron energy [MeV] 15
ALARA/IEAF-2001 vs. FISPACT/EAF-99 10 15 1m 1h 1d 30d 1y 10y 100y 10 3 y Total Activity 10 4 y 10 5 y 10 6 y 10 14 55 Fe 10 13 Eurofer activation in Demo first wall Activity, Bq/kg 10 12 10 11 10 10 3 H FISPACT/EAF-99: dashed with symbols ALARA/IEAF-2001: straight lines 10 9 10 8 14 C 53 Mn 10 7 10-2 10-1 10 0 10 1 10 2 10 3 10 4 10 5 10 6 10 7 10 8 10 9 10 10 Time after shutdown, hours 16