Nuclear Engineering and Technology

  • 제53권1호
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  • Pages.103-110
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  • 2021
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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A rapid modeling method and accuracy criteria for common-cause failures in Risk Monitor PSA model

  • Zhang, Bing (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd.) ;
  • Chen, Shanqi (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Lin, Zhixian (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Wang, Shaoxuan (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Wang, Zhen (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Ge, Daochuan (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Guo, Dingqing (School of Mechanical Engineering, Shanghai Jiao Tong University) ;
  • Lin, Jian (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd.) ;
  • Wang, Fang (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) ;
  • Wang, Jin (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)
  • 투고 : 2020.01.23
  • 심사 : 2020.06.13
  • 발행 : 2021.01.25
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초록

In the development of a Risk Monitor probabilistic safety assessment (PSA) model from the basic PSA model of a nuclear power plant, the modeling of common-cause failure (CCF) is very important. At present, some approximate modeling methods are widely used, but there lacks criterion of modeling accuracy and error analysis. In this paper, aiming at ensuring the accuracy of risk assessment and minimizing the Risk Monitor PSA models size, we present three basic issues of CCF model resulted from the changes of a nuclear power plant configuration, put forward corresponding modeling methods, and derive accuracy criteria of CCF modeling based on minimum cut sets and risk indicators according to the requirements of risk monitoring. Finally, a nuclear power plant Risk Monitor PSA model is taken as an example to demonstrate the effectiveness of the proposed modeling method and accuracy criteria, and the application scope of the idea of this paper is also discussed.

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과제정보

We thank other FDS Team members, and authors and contributors of references cited in this work. This work is supported by the National Natural Science Foundation of China (71671179, 51805511, 71901203, 51906249) and National Key R&D Program of China (2018YFB1900301, 2019YFE0191600).

참고문헌

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