高含量低浓缩铀燃料验证数据集候选数据综述

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
M. DeHart, J. Bess, G. Ilas
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引用次数: 0

摘要

许多先进的反应堆概念设计依赖于高含量低浓缩铀(HALEU)燃料,其浓度约为23.5 u(重量计)的19.75%。美国政府正在努力增加美国的高浓铀产量,以满足预期的需求。然而,除了国际反应堆物理实验评估项目中的一些新燃料基准规格外,用于验证包括高浓铀在内的计算模型的数据很少。然而,还有其他具有潜在价值的数据,可用于开发数据和软件验证工作中使用的质量基准。本文综述了现有的经评估的低浓铀燃料基准和一些潜在相关的新鲜高浓缩铀基准。然后介绍了在爱达荷国家实验室辐照高浓铀燃料的实验数据,这些数据来自于相对较新的高级试验反应堆辐照项目。应该对这些数据进行评估,如果有价值,应收集到详细的基准规范中,以满足基于低浓铀反应堆设计人员的需求。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels
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.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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