TY - GEN
T1 - Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data
AU - Hartanto, D.
AU - Chandler, D.
AU - Power, G.
AU - Bae, J.
AU - Burg, K.
N1 - Publisher Copyright:
© 2024 AMERICAN NUCLEAR SOCIETY. All rights reserved.
PY - 2024
Y1 - 2024
N2 - Validation of 252Cf production via computational simulation of actinide oxide ceramic-metallic, or cermet, pellet irradiations in the High Flux Isotope Reactor (HFIR) is an important ongoing activity to support the conversion of HFIR from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. Accurate predictions of 252Cf production must be demonstrated with the current HEU core to provide sufficient confidence that an LEU core can carry out this vital mission. This paper presents results from a series of studies based on current HFIR analysis tools and data from a recent Cf-252 irradiation campaign. The HFIRCON and Shift transport and depletion codes with ENDF/B-VII.0 and ENDF/B-VII.1 cross sections were used to model and simulate HFIR Cycles 479-482. The HFIRCON simulation with ENDF/B-VII.0 cross sections calculated a 252Cf mass of 90.4 mg, about 1 standard deviation lower than the measurement of 93.2 ± 2.7 mg. The results of the HFIRCON simulation with ENDF/B-VII.1 cross sections and both Shift simulations using both libraries were within 3 standard deviations of the measurement. Relative to the measured result, both tools estimated higher 252Cf masses with ENDF/B-VII.1 cross sections and lower masses with ENDF/B-VII.0. In addition to isotopic evolution evaluations, temporal fission densities and heat deposition rates were analyzed because they are important parameters for nuclear safety. The peak pellet heat deposition rate and cumulative fission density were about 2.4 kW/cm3 and 4.0 × 1020 fissions/cm3, respectively. Future work includes validation of other irradiation campaigns, evaluation of nuclear data deficiencies, and a thorough comparison of production metrics with the HEU core and a proposed LEU core.
AB - Validation of 252Cf production via computational simulation of actinide oxide ceramic-metallic, or cermet, pellet irradiations in the High Flux Isotope Reactor (HFIR) is an important ongoing activity to support the conversion of HFIR from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel. Accurate predictions of 252Cf production must be demonstrated with the current HEU core to provide sufficient confidence that an LEU core can carry out this vital mission. This paper presents results from a series of studies based on current HFIR analysis tools and data from a recent Cf-252 irradiation campaign. The HFIRCON and Shift transport and depletion codes with ENDF/B-VII.0 and ENDF/B-VII.1 cross sections were used to model and simulate HFIR Cycles 479-482. The HFIRCON simulation with ENDF/B-VII.0 cross sections calculated a 252Cf mass of 90.4 mg, about 1 standard deviation lower than the measurement of 93.2 ± 2.7 mg. The results of the HFIRCON simulation with ENDF/B-VII.1 cross sections and both Shift simulations using both libraries were within 3 standard deviations of the measurement. Relative to the measured result, both tools estimated higher 252Cf masses with ENDF/B-VII.1 cross sections and lower masses with ENDF/B-VII.0. In addition to isotopic evolution evaluations, temporal fission densities and heat deposition rates were analyzed because they are important parameters for nuclear safety. The peak pellet heat deposition rate and cumulative fission density were about 2.4 kW/cm3 and 4.0 × 1020 fissions/cm3, respectively. Future work includes validation of other irradiation campaigns, evaluation of nuclear data deficiencies, and a thorough comparison of production metrics with the HEU core and a proposed LEU core.
KW - Cf-252
KW - HFIR
KW - isotope
KW - LEU
KW - validation
UR - http://www.scopus.com/inward/record.url?scp=85202889374&partnerID=8YFLogxK
U2 - 10.13182/PHYSOR24-43447
DO - 10.13182/PHYSOR24-43447
M3 - Conference contribution
AN - SCOPUS:85202889374
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
SP - 28
EP - 37
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
PB - American Nuclear Society
T2 - 2024 International Conference on Physics of Reactors, PHYSOR 2024
Y2 - 21 April 2024 through 24 April 2024
ER -