Seismic fragility analysis for lateral supports of HTR-PM RPV - 18521
Conference
·
OSTI ID:23032671
- Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084 (China)
Since Fukushima accident, there has been increasing interest in China to study the risks of nuclear power plants under seismic events that are beyond the design basis. Two methodologies are commonly being adopted for this purpose, namely the seismic probabilistic risk assessment (SPRA) and the seismic margin assessment (SMA). Fragility analysis plays an important role as it not only provides fragility curves as input for the SPRA, but also can deduce HCLPF values for the SMA. In this paper, seismic fragilities of the lateral supports of the HTR-PM reactor pressure vessel (RPV) are studied. The lateral supports are crucial to the safety of HTR-PM RPV under seismic events. As they are located at a high elevation in the reactor building, it is expected they are one of the major contributors to the seismic risk of HTR-PM. The lateral supports are first briefly introduced in terms of structural features, load conditions and stress acceptance criteria in the engineering design. Their fragilities are then analyzed by identifying basic fragility analysis variables and determining values in terms of the median and standard deviations. The associated fragility curves are finally calculated and a HCLPF value is reported. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23032671
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
BUILDINGS
FUKUSHIMA DAIICHI NUCLEAR POWER STATION
HAZARDS
HTGR TYPE REACTORS
NUCLEAR POWER PLANTS
PRESSURE VESSELS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR DESIGN
REACTOR SAFETY
RISK ASSESSMENT
SAFETY STANDARDS
SEISMIC EVENTS
42 ENGINEERING
BUILDINGS
FUKUSHIMA DAIICHI NUCLEAR POWER STATION
HAZARDS
HTGR TYPE REACTORS
NUCLEAR POWER PLANTS
PRESSURE VESSELS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR DESIGN
REACTOR SAFETY
RISK ASSESSMENT
SAFETY STANDARDS
SEISMIC EVENTS