Analytical Sensitivity Analysis of a Spent Nuclear Fuel Cask

IF 0.5 Q4 ENGINEERING, MECHANICAL Journal of Verification, Validation and Uncertainty Quantification Pub Date : 2022-07-15 DOI:10.1115/1.4055013
T. Remedes, S. Ramsey, J. Baciak
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Abstract

Nuclear science and engineering is a field increasingly dominated by computational studies resulting from increasingly powerful computational tools. As a result, analytical studies which previously pioneered nuclear engineering are increasingly viewed as secondary or unnecessary. However, analytical solutions to reduced-fidelity models can provide important information concerning the underlying physics of a problem, and aid in guiding computational studies. Similarly, there is increased interest in sensitivity analysis studies. These studies commonly use computational tools. However, providing a complementary sensitivity study of relevant analytical models can lead to a deeper analysis of a problem. This work provides the analytical sensitivity analysis of the 1D cylindrical monoenergetic neutron diffusion equation using the Forward Sensitivity Analysis Procedure developed by D. Cacuci. Further, these results are applied to a reduced-fidelity model of a spent nuclear fuel cask, demonstrating how computational analysis might be improved with a complementary analytic sensitivity analysis.
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乏核燃料桶分析灵敏度分析
核科学与工程是一个由日益强大的计算工具所主导的计算研究领域。因此,以前作为核工程先驱的分析性研究越来越被视为次要的或不必要的。然而,降低保真度模型的解析解可以提供有关问题的潜在物理的重要信息,并有助于指导计算研究。同样,人们对敏感性分析研究的兴趣也在增加。这些研究通常使用计算工具。然而,提供相关分析模型的补充敏感性研究可以导致对问题的更深入的分析。本文采用D. Cacuci开发的前向灵敏度分析程序对一维圆柱形单能中子扩散方程进行了灵敏度分析。此外,这些结果应用于乏核燃料桶的降低保真度模型,证明了如何通过补充分析灵敏度分析来改进计算分析。
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来源期刊
CiteScore
1.60
自引率
16.70%
发文量
12
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