Present Status of JEFF-3.1 Qualification for LWR. Reactivity and Fuel Inventory Prediction
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1 Present Status of JEFF-3.1 Qualification for LWR Reactivity and Fuel Inventory Prediction Experimental Validation Group (CEA Cadarache/Saclay) D. BERNARD A. COURCELLE N. HFAEIDH O. LITAIZE S. MENGELLE A. SANTAMARINA T. SARGENI C. VAGLIO-GAUDARD J.F. VIDAL
2 Summary: B 2 m and k eff experimental validation for UO 2 and MOx lattices at Beginning of Cycle Fuel Inventory Prediction using JEFF-3.1
3 LWR mock-up in EOLE Facility (EPICURE-MOx Lattice) Material Buckling Experimental Validation: Pin cell calculation EPICURE UH-1.2 MISTRAL-1 MISTRAL-2 MISTRAL-3 UO X ( 235 U: 3.7% (w/o)) UO X ( 235 U: 3.7% (w/o)) MO X (7% Pu content) MO X (7% Pu content) : 1,26cm R m =1,2 : 1,32cm R m =1,7 : 1,32cm R m =1,7 : 1,39cm R m =2,0 Experiment 0 ± ± ± ± 350 APOLLO2 B 2 m (pcm) JEF JEFF Technological and experimental uncertainties
4 k eff Experimental Validation («homogeneous» core with regular lattice) Whole Core Calculation EPICURE UH-1.2 MISTRAL-1 MISTRAL-2 MISTRAL-3 k eff values UO X ( 235 U: 3.7% (w/o)) UO X ( 235 U: 3.7% (w/o)) MO X (7% Pu content) MO X (7% Pu content) : 1,26cm R m =1,2 : 1,32cm R m =1,7 : 1,32cm R m =1,7 : 1,39cm R m =2,0 Experiment 1, , , ,00057 APOLLO2 JEF-2.2 1, , , ,00818 JEFF-3.1 1, , , ,00809 TRIPOLI4 JEFF-3.1 1,0028 (2) 1,0026 (2) 1,0072 (2) 1,0081 (2)
5 k eff Experimental Validation («homogeneous» core with regular lattice) Whole Core Calculation EPICURE UH-1.2 MISTRAL-1 MISTRAL-2 MISTRAL-3 k eff values UO X ( 235 U: 3.7% (w/o)) UO X ( 235 U: 3.7% (w/o)) MO X (7% Pu content) MO X (7% Pu content) : 1,26cm R m =1,2 : 1,32cm R m =1,7 : 1,32cm R m =1,7 : 1,39cm R m =2,0 Experiment 1, , , ,00057 APOLLO2 JEF-2.2 1, , , ,00818 JEFF-3.1 1, , , ,00809 TRIPOLI4 JEFF-3.1 1,0028 (2) 1,0026 (2) 1,0072 (2) 1,0081 (2) ρ (JEF-2.2 JEFF-3.1) UOx components: ρ (JEF-2.2 JEFF-3.1) MOx components: - 400pcm : 235 U +200pcm : 238 U - 100pcm : 9i Zr - 300pcm XS S(α,β) +130pcm : 238 U +110pcm : 239 Pu +160pcm : 240 Pu - 180pcm : 241 Pu - 330pcm : 241 Am - 80pcm : 9i Zr +150pcm :H 2 O 0pcm
6 k eff Experimental Validation («homogeneous» core with regular lattice) Whole Core Calculation EPICURE UH-1.2 MISTRAL-1 MISTRAL-2 MISTRAL-3 k eff values UO X ( 235 U: 3.7% (w/o)) UO X ( 235 U: 3.7% (w/o)) MO X (7% Pu content) MO X (7% Pu content) : 1,26cm R m =1,2 : 1,32cm R m =1,7 : 1,32cm R m =1,7 : 1,39cm R m =2,0 Experiment 1, , , ,00057 APOLLO2 JEF-2.2 1, , , ,00818 JEFF-3.1 1, , , ,00809 TRIPOLI4 JEFF-3.1 1,0028 (2) 1,0026 (2) 1,0072 (2) 1,0081 (2) Reactivity of LWR-UOx cores well predicted (+100 ± 200pcm) Reactivity of 100% MOx cores overestimated (+700 ± 300pcm)
7 Reactivity effect of zirconium-isotopes evaluations (vs JEF-2.2 natural element evaluation) nat Zr 90, 91, 92, 94, 96 Zr MISTRAL-2 (MOx): APOLLO2: ρ(nat/iso) = - 92pcm TRIPOLI4: ρ(nat/iso) = - 80pcm (30)
8 Reactivity effect of zirconium-isotopes evaluations (vs JEF-2.2 natural element evaluation) nat Zr 90, 91, 92, 94, 96 Zr MISTRAL-2 (MOx): APOLLO2: ρ(nat/iso) = - 92pcm TRIPOLI4: ρ(nat/iso) = - 80pcm (30) Mainly due to 91 Zr (n,γ) modification, particularly in the 292eV resonance
9 Post Irradiation Experiment UOx Spent Fuel Inventory Experimental Validation using JEFF-3.1: Comparison between Depletion Calculations and Spent Fuel Radio-chemical Assays
10 Post Irradiation Experiment GRAVELINES PWR 3 fuel rods 235 U 4.5% (w/o) 60GWd/t C/E - 1 (%) JEF-2.2 C/E - 1 (%) JEFF-3.1 Experimental Uncertainties (δ E/E) 234 U/ 238 U 1,8 4,3 3,0 235 UI γ 236 U/ 238 U -4,2-0,7 0,6 235 U/ 238 U 4,6 2,1 3,5 237 Np/ 238 U -6,5-1,3 3,2 N 236U 238 U(n,γ) XS U(n,2n) 238 Pu/ 238 U -10,2-9,0 3,7 239 Pu/ 238 U 1,4 0,4 1,3 240 Pu/ 238 U -0,7 0,4 1,1 241 Pu/ 238 U -2,3-3,0 1,6 242 Pu/ 238 U -8,6-3,1 2,8 241 Am/ 238 U (EOI) 5,8 0,1 5,0 242M Am/ 238 U -21,6 2,3 7,1 243 Am/ 238 U -8,7-2,4 4,4 243 Cm/ 238 U -19,2-26,5 6,3 244 Cm/ 238 U -16,8-11,2 4,3 (Γγ) 241 Pu 0.26eV 245 Cm/ 238 U -17,8-17,9 5,9 246 Cm/ 238 U -29,2-32,2 7,0 247 Cm/ 238 U -16,0-1,3 9,6 143 Nd/ 238 U 1,4-0,7 1,2 241 Am(n,γ) XS & Isomeric Ratio 144 Nd/ 238 U -2,1-0,5 3,1 145 Nd/ 238 U -0,4-0,4 1,5 146 Nd/ 238 U 0,9 1,3 2,4 148 Nd/ 238 U 1,5 1,4 2,1 150 Nd/ 238 U 0,7 0,7 2,3 FP fission yields 133 Cs/ 238 U -4,4-3,2 1,3 134 Cs/ 238 U -0,7-1,9 2,4 135 Cs/ 238 U -3,8-4,9 2,6 137 Cs/ 238 U -5,8-6,4 2,1
11 Conclusion Preliminary JEFF-3.1 qualification results : k eff prediction for : LWR-UOx : (C JEFF-3.1 E) = +100 ± 200pcm (JEF-2.2: +480pcm) LWR-MOx : (C JEFF-3.1 E) = +700 ± 300pcm (JEF-2.2: +710pcm) PIE prediction for UOx fuels is improved thanks to 235,238 U, 241 Pu, 241 Am XS and isomeric ratios evaluations. Additional work is needed : PIE prediction for MOx fuels Reactivity loss in depletion (UOx and MOx spent fuel oscillations in MINERVE Facility) Separated isotopes oscillation (2% accuracy) is in progress: OSMOSE: actinides from 232 Th to Cm OCEAN: neutronic absorbers (Gd + Hf + Er )
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