Results 151 to 160 of about 530 (190)

Development of efficient complete-sampling-based seismic PSA method for nuclear power plant

Reliability Engineering and System Safety, 2020
Abstract In this study, we propose an enhanced complete-sampling-based seismic PSA quantification technique that can precisely treat the partial correlations among components of seismic fragility information. Specifically, we have developed an improved seismic PSA quantification code by combining advantages of two representative methodologies: EPRI ...
Shinyoung Kwag, In-Kil Choi
exaly   +2 more sources

Seismic PSA method for multiple nuclear power plants in a site

Reliability Engineering and System Safety, 2007
The maximum number of nuclear power plants in a site is eight and about 50% of power plants are built in sites with three or more plants in the world. Such nuclear sites have potential risks of simultaneous multiple plant damages especially at external events.
exaly   +2 more sources

Analysis of common cause failure effect on system reliability in seismic PSA

Progress in Nuclear Energy, 2014
Abstract In seismic PSA of nuclear power plant, the equipment failure probability is affected by two parts – response and fragility. In this paper causations of CCF in the above two parts is analyzed, the sensitivity of CCF factor is evaluated under different peak ground acceleration levels.
Shengfei Wang, Fenglei Niu
exaly   +2 more sources

Relay Chatter Analysis With Practical Application in Seismic PSA in Nuclear Power Station

Volume 13: Risk Assessments and Management, 2022
Abstract In the seismic PSA analysis of a nuclear power plant, the relay chatter analysis is a unique and important research content. An earthquake may cause inadvertent vibration of the relay contacts with an undesired output due to the low seismic ruggedness, and if the chatter time sustained more than 2 milliseconds, it will give an ...
Jianfeng Yang, Xiaohui Gu, Bingchen Feng, Hangding Wang   +3 more
exaly   +2 more sources

Study of rationalized safety design based on the seismic PSA for an LMFBR

Reliability Engineering and System Safety, 1998
Abstract Seismic PSA was carried out for a typical liquid metal cooled fast breeder reactor (LMFBR) in order to study the rationalized seismic design, maintaining and/or improving safety during seismic event. The seismic sequence quantification identifies the dominant structures, systems and components (SSCs) to the seismic core damage frequency (CDF)
Akira Yamaguchi
exaly   +2 more sources

Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China

Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, 2020
Abstract Level 2 (L2) PSA is focused on the severe accident phenomenon, progression and source terms release to generally evaluate the containment response after core damage takes place. Fukushima accident was caused by seismic and tsunami which are beyond design basis. It indicates that evaluating the risk for extremely external hazards
Liu Yu, Li Wenjing, Yu Yun
exaly   +2 more sources

The calculation of component failure probability in the seismic PSA using Monte Carlo sampling

Proceedings of International Conference on Information Systems for Crisis Response and Management (ISCRAM), 2011
According to the experience in Probabilistic safety assessment (PSA) studies of operating NPPs, one of the most important external events affecting NPP safety is earthquakes. The seismic PSA evaluates the risks of severe accidents at nuclear power plants (NPPs) caused by seismic events.
Chang-hong Peng, Jun Xiao, Ning Zhang
exaly   +2 more sources

Development of the DQFM method to consider the effect of correlation of component failures in seismic PSA of nuclear power plant

Reliability Engineering and System Safety, 2003
Abstract This paper presents a new calculation method for considering the effect of correlation of component failures in seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs) by direct quantification of Fault Tree (FT) using the Monte Carlo simulation (DQFM) and discusses the effect of correlation on core damage frequency (CDF).
Yuichi Watanabe, Tetsukuni Oikawa, Ken Muramatsu   +2 more
exaly   +2 more sources

Treatment of Dependency and Correlation in Multiunit PSA Considering Seismic as External Event

Transactions of the Indian National Academy of Engineering, 2023
Gopika Vinod, M Hari Prasad, Vinod Gopika   +2 more
exaly   +2 more sources

Research on Correlation Analysis Methods for Equipment Seismic Failure in Seismic PSA

Springer Proceedings in Physics
Jianfeng Yang, Qian Huang, Long Li, Xipeng Yu   +3 more
exaly   +2 more sources