Accurate Nuclear Data Validation Studies and Trends
Identification and validation of benchmark experiments for nuclear data libraries, comparison with different models and codes, sensitivity calculations, identification of uncertainties, and contributors. Activities of IRSN and NRG showcased at the Final SANDA Meeting in July 2024.
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SUPLYING ACCURATE NUCLEAR DATA FOR ENERGY AND NON-ENERGY APPLICATIONS WP5. Nuclear data validation and integral experiments WP5. Nuclear data validation and integral experiments Task 5.2 Task 5.2 Validation studies (using existing experiments) Validation studies (using existing experiments) Subtask 5.2.2 Subtask 5.2.2 C/E validation and trends C/E validation and trends Deliverable 5.8: Deliverable 5.8: Report on critical benchmark C/E validation and Report on critical benchmark C/E validation and nuclear data trends nuclear data trends Contributors: Contributors: IRSN: N. Leclaire, L. Leal NRG: S.C. van der Marck Final SANDA Meeting, July 2024 Final SANDA Meeting, July 2024 Final SANDA Meeting, July 2024 EU DuC = X SLIDE 1
SUPLYING ACCURATE NUCLEAR DATA FOR ENERGY AND NON-ENERGY APPLICATIONS Deliverable 5.8 Deliverable 5.8 (critical benchmark C/E validation and nuclear data trends) Status Approved Dissemination Work presented at JEFF meetings Numerical results submitted to NEA Databank JEFF project MCNP ( Serpent) models shared, available at NEA Databank Final SANDA Meeting, July 2024 Final SANDA Meeting, July 2024 Final SANDA Meeting, July 2024 EU DuC = X SLIDE 2
IRSN and NRG Identification of a set of integral benchmark experiments to contribute to the validation of the JEFF-33 and JEFF- 4.0-T(1,2,3) nuclear data libraries 182 cases from the MORET 5 validation database 576 cases from the NRG validation database 120 cases in common comparable results achieved with different models & codes Processing of nuclear data : IRSN with GAIA 1.1.2 based on NJOY2016 NRG based on NJOY2016 (v68 for JEFF-4t2) Calculation of the benchmark results : IRSN with continuous energy code MORET 5 NRG with continuous energy code MCNP 6.2 Sensitivity calculation with IFP methodology (both MORET 5 and MCNP 6.2) Identification of biases thru comparison with benchmark keffand experimental uncertainties Identification of the main contributors to the uncertainty with sensitivity coefficients Final SANDA Meeting, July 2024 EU DuC = X SLIDE 3
IRSN activities (I) [ Keffresults with recent evaluations are generally in good agreement with the benchmark, considering the uncertainty margin lct27 207Pb MT2 Final SANDA Meeting, July 2024 EU DuC = X SLIDE 4
IRSN activities (II) [ The evaluations of 56Fe in the epithermal energy range with JEFF-3.3 and JEFF-4T1 lead to keff values that are further from the benchmark compared with ENDF/B-VIII.0 Final SANDA Meeting, July 2024 EU DuC = X SLIDE 5
NRG activities (I) For fast spectrum benchmarks with (almost) only uranium, the performance of JEFF-4t2 is similar to JEFF-3.3 and ENDF/B-VIII.0 For a number of HEU cases there appears to be a subtle trend with EALF; it is not clear whether this trend is due to the benchmarks or due to the data Final SANDA Meeting, July 2024 EU DuC = X SLIDE 6
NRG activities (II) For fast spectrum plutonium benchmarks, the results are in good agreement with the benchmark values (except for JEF-2.2) For a number of cases where this is not the case, the deviation can be attributed to the nuclear data of reflector material (e.g. Al and Ti in JEFF-4T1) Final SANDA Meeting, July 2024 EU DuC = X SLIDE 7
Concluding remarks SUPLYING ACCURATE NUCLEAR DATA FOR ENERGY AND NON-ENERGY APPLICATIONS Benchmark calculations have been performed for each test release of JEFF-4: 4T0: JEFDOC-2090, JEFDOC-2094 4T1: JEFDOC-2140, JEFDOC-2143 4T2: JEFDOC-2172, JEFDOC-2173 4T3: JEFDOC-2350 The feedback from these calculations has enabled iterative improvements of nuclear data for the major actinides as well as several reflector materials, contributing to the quality of the final JEFF-4.0 release (planned for the end of 2024) Final SANDA Meeting, July 2024 EU DuC = X SLIDE 8
