Correction Factors derived from the recent JEFF3.1.1 Library for PWR-UOx BUC applications C. Riffard, A. Santamarina, L. San Felice CEA, DEN, DER, SPRC, CEA-Cadarache, F-13108 Saint Paul-Lez-Durance International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 1 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
INTRODUCTION BUC Methodology The recent BUC methodology developed by CEA in collaboration with AREVA- NC is accounting for: Actinides + 15 Fission Products (stable and non-gazeous) Conservative hypothesis for the depletion calculation Qualification Reports for spent fuel inventory calculation and reactivity worth of BUC nuclides : Isotopic Correction Factors Bounding axial burnup profile of spent fuel assemblies (Session III, 3.3) Main references : ICNC’95, FJSS’98, PHYSOR2002, TMC2005, ICNC’07 International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 2 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
French PWR UO 2 BUC Calculation Route / BUC nuclides Actinides : 234 U, 235 U, 236 U, 238 U, 237 Np, 238 Pu, 239 Pu, 240 Pu, 241 Pu, 242 Pu, 241 Am, 243 Am 15 FPs : 95 Mo, 99 Tc, 101 Rh, 103 Rh, 109 Ag, 133 Cs, 143 Nd, 145 Nd, 147 Sm, 149 Sm, 150 Sm, 151 Sm, 152 Sm, 153 Eu, 155 Gd International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 3 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Spent Fuel inventory calculation : DARWIN2.3 package JEFF3.1.1 CEA2005V4 ERALIB ECCO APOLLO2 ERANOS CRONOS ( φ, σ n ) g Collapsed reaction Fuel Cycle Library (JEFF3.1.1, EAF) rates DARWIN/ PEPIN2.2.3 Evolution chain Depletion calculation Phys. OUTPUTS Specific nuclear constants Concentrations Library BUC experimental Program 1/ PIE for the validation of Spent Fuel Inventory Calculation - Destructive analysis of fuel rod cuts from PWR-UO 2 assemblies - Accurate measurements of isotopic content with mass-spectrometry techniques International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 4 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Criticality calculations : CRISTAL V1 package BUC experimental Program 2/ Oscillations experiments in the MINERVE reactor : reactivity worth of individual FPs and overall [actinides + FP] vs BU Samples of separated FP isotopes in UO 2 pellets, natural elements in Al 2 O 3 matrix, Spent fuel samples, Calibration samples ( 235 U, Borated UO 2 ) International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 5 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Spent fuel inventory calculation biases 1/ Validation of the DARWIN 2 Depletion Code for SF inventory Calculation route : Validated reference sheme ‘REL2005’ of the APOLLO2.8 package ref J-F VIDAL et al., « New Modelling of LWR Assemblies using the APOLLO2 Code Package », M&C2007, Monterey (USA). Depletion calculation • Accurate description of Operating Power (PEPIN2) • Fuel, Clad and Moderator Temperatures calculated with a thermo- mechanics code (METEOR) • ‘Effective Temperature’ of fuel ( 238 U capture rate) • Mean Boron concentration + Stretch-out modelisation Calculation to experiment comparison • PWR UO 2 BUC database : 235 U Init : 3.1% to 4.5% – – BU : 15 to 60 GWd/t – 22 samples uncertainty ( σ ) versus burnup • (C-E)/E versus burnup Full Propagation of errors: Chemical analysis, Burnup determination, Mod. Temp., Fuel Temp., Operating History International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 6 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Spent fuel inventory calculation biases 4 DARWIN 2.3 + CEA2005V4 C/E + sigma +1 JEFF3 trend 0 -1.6 (C/E)-1 (%) C/E + sigma JEF2.2 trend JEFF3.1.1 -4 -8 JEF2.2 -12 15000 25000 35000 45000 55000 65000 BU (MWd/t) 242 Pu Calculation – Experiment deviation in part of the French P.I.E. database The linear trends are calculated on the whole PIE database σ ] BU = retained value for the determination of CF Maximum deviation [(C-E)/E excepted 235 U and 239 Pu (exact linear trend retained) International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 7 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Spent fuel inventory calculation biases 20 C/E + sigma DARWIN 2.3 + CEA2005V4 +17.5 JEF2.2 trend 15 ~50 pcm (C/E)-1 (%) 10 C/E + sigma +5.5 JEFF3 trend 5 0 -5 15000 25000 35000 45000 55000 65000 BU (MWd/t) 153 Eu Calculation – Experiment deviation in part of the French P.I.E. (The linear trends are calculated on the whole PIE database) International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 8 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Spent fuel inventory calculation biases 20 DARWIN 2.3 + CEA2005V4 +15.5 C/E + sigma JEF2 trend 10 (C/E)-1 (%) ~ 180 pcm C/E + sigma +3 JEFF3 trend 0 -10 15000 25000 35000 45000 55000 65000 BU (MWd/t) 155 Gd Calculation – Experiment deviation in part of the French P.I.E. database (The linear trends are calculated from the whole PIE database) International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 9 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Partial Correction Factors The application of these correction factors enables us to correct the underestimation of some fissile isotopes and the overestimation of some absorbent isotopes for the total calculated reactivity worth; If it is not the case, Fc = 1 (the calculated concentration is not modified), in order to maintain the conservatism of the concentration. Partial Correction Isotope Factor JEFF3 236 U 0.99 240 Pu 0.99 241 Pu 1.08 242 Pu 0.99 241 Am 0.98 133 Cs 1 143 Nd 0.99 151 Sm 1 152 Sm 1 153 Eu 0.95 155 Gd 0.97 International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 10 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
FP Reactivity w orth calculation biases 2/ Validation of the CRISTAL V1 code for FP poisoning worth calculation Calculation route: deterministic transport Code APOLLO2.5 in CRISTAL V1; experiment analysis by Exact Perturbation Theory • Limited multicell geometry 2-D 11x11 • Pij – UP1 model From (C-E)/E bias in R1-UO2 (LWR experimental lattice) uncertainty ( σ) for each FP isotope (C-E)/E Ref Santamarina et al., ICNC95 Minerve core Quadratic combinaison of errors: Chemical analysis of the sample material balance, experimental uncertainty of ∆ (sample – reference) signal, calibration of the experimental worth signal Central cavity: Water pool Graphite MTR Test lattice reflector bundle International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 11 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
FP Reactivity w orth calculation biases JEF2.2 results Calculation – experiment biases of FP poisoning worth in R1-UO2 with CRISTAL V1 (C-E)/E Uncertainty Isotope [%] [%] Sm-149 -5.7 2.1 Nd-143 -4.5 2.5 Rh-103 13.3 4.0 Cs-133 4.3 1.9 Gd-155 -1.9 2.9 Sm-152 -0.2 3.2 Nd-145 0.4 4.1 Mo-95 -3.6 3.4 Eu-153 -1.6 4.4 Ag-109 -1.7 4.0 Tc-99 4.2 3.8 Maximum deviation [(C-E)/E + σ ] = retained value for the determination of CF International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 12 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
FP Reactivity w orth calculation biases Improvements in JEFF3.1.1 : new FP evaluations A. S SANTAM AMARI ARINA e A et al., JEF-DOC 1263 1263 International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 13 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
Isotopic Correction factors 4/5 Global Correction Factors applied to the BUC nuclides calculated with DARWIN2 / JEF2.2 for criticality calculations involving PWR-UO2 fuels Actinides CF Fission Product CF 234 U 95 Mo 0.94 0.94 Improvement of the spent 235 U 99 Tc 1.01 0.87 fuel inventory bias with 236 U 101 Ru 0.98 0.70 CEA2005V4 for: 237 Np 103 Rh 0.98 0.80 Pu242 238 Pu 109 Ag 1.00 1.00 Am241 240 Pu 133 Cs Nd143 0.97 0.96 Sm147 241 Pu 143 Nd 1.06 0.98 Sm151 242 Pu 145 Nd 0.99 0.94 Sm152 241 Am 147 Sm 0.94 0.99 Eu153 243 Am 149 Sm 0.98 0.97 Gd155 150 Sm 0.97 151 Sm 0.84 152 Sm 0.90 153 Eu 0.83 155 Gd 0.86 International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 14 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
In conclusion … Full BUC approach based on Global Isotopic Correction Factors applied in front of the criticality calculation, derived from the Qualification reports of the French reference codes : DARWIN 2.3 Spent Fuel inventory calculation CRISTAL Criticality and FP reactivity worth calculation The recommended fuel cycle Library CEA2005V4 Forthcoming : Significant reduction of the global CF / JEF2.2 due to the CEA2005V4 library for 147 Sm, 151 Sm, 152 Sm, 153 Eu and 155 Gd isotopes + improvement of 99 Tc reactivity worth prediction. International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, 15 Reprocessing and Disposition – Cordoba, 27-30, Oct. 2009
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