An internal flood probabilistic safety assessment (IFPSA) identifies risk-significant flood areas, components and scenarios, and evaluates the risk that a nuclear power plant (NPP) faces under internal flood conditions. This paper draws a comparison between NPPs in operation and those in the design stage with regards to the performance of IFPSA, and the main differences are shown in such tasks as flood area identification, flood source and SSC identification, plant walkdown, flood scenario characterization, flood frequency quantification and flood consequence analysis. Specific cases are presented in order to illustrate the application of IFPSA in NPP design to assess risks, identify potential weak links and provide insights into possible design modifications regarding internal flood protection.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5782-3
PROCEEDINGS PAPER
Performance and Application of Internal Flood Probabilistic Safety Assessment in Nuclear Power Plant Design
Lihua Huang,
Lihua Huang
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
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Xiang Liu,
Xiang Liu
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
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Lijuan Wang
Lijuan Wang
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
Search for other works by this author on:
Lihua Huang
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
Xiang Liu
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
Lijuan Wang
Suzhou Nuclear Power Research Institute Co., Ltd, Shenzhen, China
Paper No:
ICONE25-66398, V004T14A014; 5 pages
Published Online:
October 17, 2017
Citation
Huang, L, Liu, X, & Wang, L. "Performance and Application of Internal Flood Probabilistic Safety Assessment in Nuclear Power Plant Design." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management. Shanghai, China. July 2–6, 2017. V004T14A014. ASME. https://doi.org/10.1115/ICONE25-66398
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