Results 141 to 150 of about 414,163 (176)
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Study of rationalized safety design based on the seismic PSA for an LMFBR
Reliability Engineering and System Safety, 1998Abstract 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
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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, 2020Abstract 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
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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), 2011According 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
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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 +2 more
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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 +2 more
exaly +3 more sources
The use of the uniform risk spectra in the seismic PSA for a PWR power station
Nuclear Engineering and Design, 1995Abstract This paper describes a simple method for incorporating the effects of the uniform risk spectra (URS) in the seismic probabilistic safety assessment (PSA) for a pressurized water reactor (PWR) power station. The “traditional” fragility parameters for a range of critical equipment items in a PWR power station on two typical UK sites are ...
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Treatment of Dependency and Correlation in Multiunit PSA Considering Seismic as External Event
Transactions of the Indian National Academy of Engineering, 2023Gopika Vinod
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Research on Correlation Analysis Methods for Equipment Seismic Failure in Seismic PSA
Springer Proceedings in PhysicsJianfeng Yang +3 more
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Portable Seismic Acquistion System (Psas) For Pavement Masw
15th EEGS Symposium on the Application of Geophysics to Engineering and Environmental Problems, 2002A seismic method (e.g., surface- or body-wave method) has been often used in pavement engineering to evaluate such critical constructional parameters as the E-modulus and Poisson’s ratio. Conventional method usually uses one or two-channel recording device (e.g., dynamic signal analyzer) for data acquisition whose cost is by no means trivial.
Nils Ryden +3 more
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Quantitative Method for Seismic PSA Optimization Based on Binary Decision Diagrams
Springer Proceedings in PhysicsSong Jinyang +4 more
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Preliminary Analysis of Seismic Shutdown PSA of a PWR plant
18th International Conference on Nuclear Engineering: Volume 3, 2010Shutdown seismic PSA was performed for the plant cold shutdown condition. Normally, automatic ECCS signal is blocked after the Permission Signal is indicated during the plant cooldown process of PWR. In response to this, PSA model including manual actuation of ECCS signal on the postulated LOCA condition during cold shutdown state was developed based ...
Keisuke Kondo +3 more
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