Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant

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作者信息关键词期刊信息基础信息归属信息摘要

成果类型：

期刊论文

作者：

Chen, Shuai;Zhang, Li;Qing, Tao;Liu, Xueyang

通讯作者：

Li Zhang

作者机构：

[Chen, Shuai; Zhang, Li] Univ South China, Coll Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.

[Qing, Tao; Zhang, Li; Liu, Xueyang] Hunan Inst Technol, Inst Human Factor Engn & Safety Management, Hengyang 421002, Hunan, Peoples R China.

通讯机构：

[Li Zhang] C

College of Nuclear Science and Technology, University of South China, Hengyang, Hunan, People's Republic of China<&wdkj&>Institute of Human Factor Engineering＆Safety Management, Hunan Institute of Technology, Hengyang, Hunan, People's Republic of China

语种：

英文

关键词：

Bayesian networks;Core disruptive accidents;Human resource management;Nuclear energy;Nuclear fuels;Outages;Reliability analysis;Risk analysis;Risk assessment;Cognitive functions;Failure Probability;Human reliability analysis;Performance influencing factors;Performance shaping factors;Probabilistic Risk Assessment;Reactor cooling systems;Severe accident management guidelines;Nuclear power plants

期刊：

Journal of Nuclear Science and Technology

ISSN：

0022-3131

年：

2021

卷：

期：

页码：

1099-1112

DOI：

10.1080/00223131.2021.1915893

基金类别：

This research was supported by the National Natural Science Foundation of China (Grant Nos.71371070,71771084), Hunan Provincial Innovation Foundation For Postgraduate (No.CX20200908), The Provincial Characteristic Application Discipline of Safety Science and Engineering of Hunan Institute of Technology (KFB20020).

机构署名：

本校为第一机构

院系归属：

核科学技术学院

摘要：

Human reliability analysis (HRA) for severe accidents is an important component of a Level 2 probabilistic risk assessment (PRA) for nuclear power plants. In this study, a Bayesian network (BN) is used to construct a qualitative causal model of human error during severe accidents by identifying the main cognitive functions (MCFs), crew failure modes (CFMs), and performance influencing factors (PIFs) for emergency personnel implementing severe accident management guidelines (SAMGs) after core damage. This qualitative model is used to develop a q...

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Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant

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