4.7 Article

Accelerated statistical failure analysis of multifidelity TRISO fuel models

期刊

JOURNAL OF NUCLEAR MATERIALS
卷 563, 期 -, 页码 -

出版社

ELSEVIER
DOI: 10.1016/j.jnucmat.2022.153604

关键词

Monte Carlo; Variance reduction; Bison; Nuclear fuel; Risk; Reliability

资金

  1. INL's Laboratory Directed Research & Development (LDRD) program under DOE Idaho Operations Office [DE-AC07-05ID14517]
  2. Office of Nuclear Energy of the U.S. DOE [DE-AC07-05ID14517]
  3. Nuclear Science User Facilities [DE-AC07-05ID14517]

向作者/读者索取更多资源

This paper presents four statistical methods for fuel failure analysis in Bison, using TRISO-coated particle fuel as a case study. Among these methods, subset simulation (SS) and the Weibull theory are deemed the most efficient, and can be applied to both 1-D and 2-D TRISO models to compute failure probabilities.
Statistical nuclear fuel failure analysis is critical for the design and development of advanced reactor technologies. Although Monte Carlo Sampling (MCS) is a standard method of statistical failure analysis for fuels, the low failure probabilities of some advanced fuel forms and the correspondingly large number of required model evaluations limit its application to low-fidelity (e.g., 1-D) fuel models. In this paper, we present four other statistical methods for fuel failure analysis in Bison, considering tri-structural isotropic (TRISO)-coated particle fuel as a case study. The statistical methods considered are Latin hyper cube sampling (LHS), adaptive importance sampling (AIS), subset simulation (SS), and the Weibull theory. Using these methods, we analyzed both 1-D and 2-D representations of TRISO models to compute failure probabilities and the distributions of fuel properties that result in failures. The results of these methods compare well across all TRISO models considered. Overall, SS and the Weibull theory were deemed the most efficient, and can be applied to both 1-D and 2-D TRISO models to compute failure probabilities. Moreover, since SS also characterizes the distribution of parameters that cause TRISO failures, and can consider failure modes not described by the Weibull criterion, it may be preferred over the other methods. Finally, a discussion on the efficacy of different statistical methods of assessing nuclear fuel safety is provided. (c) 2022 Elsevier B.V. All rights reserved.

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