Fire Probabilistic Risk Assessment (PRA) is one of the main methods of fire safety analysis for nuclear power plants (NPPs). At present, the fire PRA under the at-power condition has been widely studied, while the research on the low power and shutdown condition (LPSD) is quite limited. Therefore, in this paper, a second generation NPP on the east coast of China is taken as the research target, and the analysis methods are based on the latest LPSD fire PRA theory in report NUREG/CR-7114. This paper studies the initiating events and ignition frequencies of fire PRA considering the real conditions in LPSD, and established LPSD Fire PRA model, finally obtained the quantitative risk result of the core damage caused by the fire According to the results of this LPSD fire PRA, the fire risk-significant sources and fire risk weakness are found out and the improvement suggestions have been promoted.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5144-9
PROCEEDINGS PAPER
Study on Shutdown Fire PRA for Nuclear Power Plant
Meiru Liu,
Meiru Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
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Qingnan Zhao,
Qingnan Zhao
China Nuclear Power Engineering Co., Ltd., Beijing, China
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Wei Deng,
Wei Deng
China Nuclear Power Engineering Co., Ltd., Beijing, China
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Jinyan Du,
Jinyan Du
China Nuclear Power Engineering Co., Ltd., Beijing, China
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Lin Sun
Lin Sun
Harbin Engineering University, Harbin, China
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Meiru Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
Qingnan Zhao
China Nuclear Power Engineering Co., Ltd., Beijing, China
Wei Deng
China Nuclear Power Engineering Co., Ltd., Beijing, China
Jinyan Du
China Nuclear Power Engineering Co., Ltd., Beijing, China
Lin Sun
Harbin Engineering University, Harbin, China
Paper No:
ICONE26-81272, V002T14A007; 6 pages
Published Online:
October 24, 2018
Citation
Liu, M, Zhao, Q, Deng, W, Du, J, & Sun, L. "Study on Shutdown Fire PRA for Nuclear Power Plant." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management. London, England. July 22–26, 2018. V002T14A007. ASME. https://doi.org/10.1115/ICONE26-81272
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