A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

DeHart, Mark D.; Bess, John Darrell; Ilas, Germina

doi:10.3390/jne4030038

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

Journal Article · Wed Aug 16 00:00:00 EDT 2023 · Journal of Nuclear Engineering

DOI:https://doi.org/10.3390/jne4030038· OSTI ID:2204569

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)
JFoster and Associates, Idaho Falls, ID (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Many advanced reactor concept designs rely on high-assay low-enriched uranium (HALEU) fuel, enriched up to approximately 19.75% ²³⁵U by weight. Efforts are underway by the US government to increase HALEU production in the United States to meet anticipated needs. However, very few data exist for validation of computational models that include HALEU, beyond a few fresh fuel benchmark specifications in the International Reactor Physics Experiment Evaluation Project. Nevertheless, there are other data with potential value available for developing into quality benchmarks for use in data- and software-validation efforts. This paper reviews the available evaluated HALEU fuel benchmarks and some of the potentially relevant benchmarks for fresh highly enriched uranium. It then introduces experimental data for HALEU fuel irradiated at Idaho National Laboratory, from relatively recent irradiation programs at the Advanced Test Reactor. Such data should be evaluated and, if valuable, collected into detailed benchmark specifications to meet the needs of HALEU-based reactor designers.

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS)

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517

OSTI ID:: 2204569

Journal Information:: Journal of Nuclear Engineering, Journal Name: Journal of Nuclear Engineering Journal Issue: 3 Vol. 4; ISSN 2673-4362

Publisher:: MDPICopyright Statement

Country of Publication:: United States

Language:: English

References (13)

Testing of cross section libraries on zirconium benchmarks Snoj, Luka; Trkov, Andrej; Ravnik, Matjaž Annals of Nuclear Energy, Vol. 42 https://doi.org/10.1016/j.anucene.2011.12.001	journal	April 2012
Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE Ilas, Germina; Gauld, Ian C.; Radulescu, Georgeta Annals of Nuclear Energy, Vol. 46 https://doi.org/10.1016/j.anucene.2012.03.012	journal	August 2012
SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data Michel-Sendis, F.; Gauld, I.; Martinez, J. S. Annals of Nuclear Energy, Vol. 110 https://doi.org/10.1016/j.anucene.2017.07.022	journal	December 2017
Scientific motivations for a reassessment of the neutron capture cross sections of erbium isotopes in the high-sensitivity thermal energy range for LWR systems Guglielmelli, A.; Rocchi, F.; Massimi, C. Annals of Nuclear Energy, Vol. 178 https://doi.org/10.1016/j.anucene.2022.109337	journal	December 2022
An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques Harp, Jason M.; Demkowicz, Paul A.; Winston, Philip L. Nuclear Engineering and Design, Vol. 278 https://doi.org/10.1016/j.nucengdes.2014.07.041	journal	October 2014
Analysis of fission gas release-to-birth ratio data from the AGR irradiations Einerson, Jeffrey J.; Pham, Binh T.; Scates, Dawn M. Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2015.11.003	journal	September 2016
The AGR-3/4 fission product transport irradiation experiment Collin, Blaise P.; Demkowicz, Paul A.; Petti, David A. Nuclear Engineering and Design, Vol. 327 https://doi.org/10.1016/j.nucengdes.2017.12.016	journal	February 2018
Benchmark Analysis of TRIGA Mark II Reactivity Experiment Using a Continuous Energy Monte Carlo Code MCNP Matsumoto, Tetsuo; Hayakawa, Nobuhiro Journal of Nuclear Science and Technology, Vol. 37, Issue 12 https://doi.org/10.1080/18811248.2000.9714995	journal	December 2000
Evaluation of Neutron Radiography Reactor LEU-Core Start-Up Measurements Bess, John D.; Maddock, Thomas L.; Smolinski, Andrew T. Nuclear Science and Engineering, Vol. 178, Issue 4 https://doi.org/10.13182/NSE14-12	journal	December 2014
AGR-1 Post Irradiation Examination Final Report Demkowicz, Paul Andrew https://doi.org/10.2172/1236801	report	August 2015
Nuclear Data Assessment for Advanced Reactors Bostelmann, Rike; Ilas, Germina; Celik, Cihangir https://doi.org/10.2172/1840202	report	December 2021
Strategies for Application of Isotopic Uncertainties in Burnup Credit Gauld, I. C. https://doi.org/10.2172/885650	report	December 2002
Key nuclear data for non-LWR reactivity analysis Bostelmann, Friederike; Ilas, Germina; Wieselquist, William A. Frontiers in Energy Research, Vol. 11 https://doi.org/10.3389/fenrg.2023.1159478	journal	April 2023

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DOE
HALEU
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advanced reactors
high-assay LEU
validation

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels

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