Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

Martinson, Sean P.; Chirayath, Sunil S.

doi:10.1016/j.anucene.2021.108441

Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

Journal Article · Wed Jun 09 00:00:00 EDT 2021 · Annals of Nuclear Energy (Oxford)

DOI:https://doi.org/10.1016/j.anucene.2021.108441· OSTI ID:1811957

Martinson, Sean P. ^[1]; Chirayath, Sunil S. ^[2]

Texas A & M Univ., College Station, TX (United States); University of Michigan
Texas A & M Univ., College Station, TX (United States)

Monte Carlo (MC) neutronics codes are used widely for academic and industrial needs. Several schemes of coupling MC neutronics code with isotope generation and depletion code exist, which are used for performing nuclear fuel depletion simulations. These simulations can estimate the inventory of isotopes in neutron irradiated nuclear reactor fuel. However, the accuracy of these simulations shall be validated through experiments. MC codes are seldom validated by isotopic benchmarks compared to criticality benchmarks. This work compiles and analyzes the fuel depletion benchmarks and validations used to analyze the performance of MC-based fuel depletion neutronics codes. Analyses of these benchmarks and validations showed that the computed concentrations of ¹³³Cs, ¹³⁵Cs, ¹³⁷Cs, ¹⁴⁸Nd, ²³⁹Pu, ²⁴⁰Pu, and ²⁴¹Pu in the irradiated fuel by the depletion codes agreed with the measured values within 10% error. However, the computed concentrations of ¹²⁵Sb, ²⁴²Cm, ²⁴³Cm, ²⁴⁴Cm, ²⁴⁵Cm, and ²⁴⁶Cm had errors more than 15% compared to the measured values. As a result, Ventina depletion code showed the most accurate predictions for the greatest number of isotope concentrations compared to ORIGEN2 and CINDER90.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of Michigan, Ann Arbor, MI (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation

Grant/Contract Number:: NA0003920

OSTI ID:: 1811957

Journal Information:: Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Vol. 161; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

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