Add to ORKGProbabilistic safety assessment in nuclear power plants (NPPs) greatly considers plant safety and optimal plant design. Plant specific data are usually recommended to analyze safety in NPPs. However, such NPP specific data are not always available in practice. This paper presents an approach by combining fuzzy numbers and expert justification to assess an NPP probabilistic failure rate in the absence of statistical data. The proposed approach illustrates a case study for high pressure core spray systems of boiling water reactors
Internationally, probabilistic safety analyses (PSA) represent the state of the art not only in the ...
Components of nuclear power plants do not always have historical failure data to probabilistically e...
Piping failure frequencies are needed e.g. for quantifying initiating event frequencies in probabili...
Probabilistic safety assessment in nuclear power plants (NPPs) greatly considers plant safety and op...
Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tre...
The Probabilistic Risk Assessment (PSA) method, popular in nuclear industry, does not provide valid ...
The objective of this study is to estimate the occurrence probabilities of severe accident phenomena...
Conventional fault tree analysis in safety analysis of complex engineering systems calculates the oc...
Fault tree analysis (FTA) is a deductive tool to assess the safety of nuclear power plants. This ana...
[EN] There is an attempt nowadays to provide a more comprehensive and realistic safety assessment of...
[[abstract]]In the probabilistic Safety Assessment (PSA), probabilistic, statistic, and reliability ...
In the framework of “rare events” problem, the probabilistic approaches tend to be inef-fective. The...
© Imperial College Press. Fault tree analysis for nuclear power plant probabilistic safety assessmen...
Safety analysis of Nuclear Power Plants (NPPs) employing digital Instrumentation and Control (I&...
This paper presents a fuzzy inference system (FIS) as an approach to estimate Nuclear Power Plant (N...
Internationally, probabilistic safety analyses (PSA) represent the state of the art not only in the ...
Components of nuclear power plants do not always have historical failure data to probabilistically e...
Piping failure frequencies are needed e.g. for quantifying initiating event frequencies in probabili...
Probabilistic safety assessment in nuclear power plants (NPPs) greatly considers plant safety and op...
Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tre...
The Probabilistic Risk Assessment (PSA) method, popular in nuclear industry, does not provide valid ...
The objective of this study is to estimate the occurrence probabilities of severe accident phenomena...
Conventional fault tree analysis in safety analysis of complex engineering systems calculates the oc...
Fault tree analysis (FTA) is a deductive tool to assess the safety of nuclear power plants. This ana...
[EN] There is an attempt nowadays to provide a more comprehensive and realistic safety assessment of...
[[abstract]]In the probabilistic Safety Assessment (PSA), probabilistic, statistic, and reliability ...
In the framework of “rare events” problem, the probabilistic approaches tend to be inef-fective. The...
© Imperial College Press. Fault tree analysis for nuclear power plant probabilistic safety assessmen...
Safety analysis of Nuclear Power Plants (NPPs) employing digital Instrumentation and Control (I&...
This paper presents a fuzzy inference system (FIS) as an approach to estimate Nuclear Power Plant (N...
Internationally, probabilistic safety analyses (PSA) represent the state of the art not only in the ...
Components of nuclear power plants do not always have historical failure data to probabilistically e...
Piping failure frequencies are needed e.g. for quantifying initiating event frequencies in probabili...