Accelerated statistical failure analysis of multifidelity TRISO fuel models

被引:10
|
作者
Dhulipala, Somayajulu L. N. [1 ]
Jiang, Wen [1 ]
Spencer, Benjamin W. [1 ]
Hales, Jason D. [1 ]
Shields, Michael D. [2 ]
Slaughter, Andrew E. [3 ]
Prince, Zachary M. [4 ]
Laboure, Vincent M. [4 ]
Bolisetti, Chandrakanth [5 ]
Chakroborty, Promit [2 ]
机构
[1] Idaho Natl Lab, Computat Mech & Mat, Idaho Falls, ID 83402 USA
[2] Johns Hopkins Univ, Dept Civil & Syst Engn, Baltimore, MD 21218 USA
[3] Idaho Natl Lab, Computat Frameworks, Idaho Falls, ID 83402 USA
[4] Idaho Natl Lab, Reactor Phys Methods & Anal, Idaho Falls, ID 83402 USA
[5] Idaho Natl Lab, Adv Reactor Technol & Design, Idaho Falls, ID 83402 USA
关键词
Monte Carlo; Variance reduction; Bison; Nuclear fuel; Risk; Reliability; MULTIDIMENSIONAL MULTIPHYSICS SIMULATION;
D O I
10.1016/j.jnucmat.2022.153604
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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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页数:18
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