Probabilistic Safety Assessment (PSA) based applications and regulations are becoming more important in the field of nuclear energy. According to the results of a PSA in Korea, the common cause failure evaluates CDF (Core Damage Frequency) as one of the significant factors affecting redundancy of NPPs. The purpose of the study is to develop a COCAP (Common Cause Failure parameter Analysis for PSA) program for the accurate use of the alpha factor model parameter data provided by other countries and for obtaining the indigenous CCF data of NPPs in Korea through Bayesian updating.This work was supported by the project of Central Research Institute, KHNP funded by the Korean government, MEST and partly supported by a BAERI program of the Nation...
Based on PSA simulations from https://data.mendeley.com/datasets/4nmvpnst8h/1, the generic PSA was s...
To estimate power plant reliability, a probabilistic safety assessment might combine failure data fr...
To assess the risk of nuclear power plant operation and to determine the risk impact of digital syst...
Analyses were performed of the safety-related performance of the reactor protection system (RPS) at ...
This master thesis investigates definitions and classifications of the common cause failure from var...
Focused attention about multi-unit probabilistic safety assessment (PSA) after the Fukushima Daiichi...
The main goal of that project was to carry out a feasibility study of a methodology devoted to evalu...
In this study, an alternative for the analysis of common cause failures (CCFs) is investigated. The ...
Currently, the risk analysis software SAPHIRE has implemented a common-cause failure (CCF) module to...
The conclusions presented in the STUK report series are those of the authors and do not necessarily ...
Data bases of five studies concerned with failure probabilities of diesel generator systems in nucle...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
Nuclear power plants are increasingly being equipped with digital I&C systems. Although some pro...
Common cause fault rates for diesel generators in nuclear power plants are estimated, using Licensee...
Internationally, probabilistic safety analyses (PSA) represent the state of the art not only in the ...
Based on PSA simulations from https://data.mendeley.com/datasets/4nmvpnst8h/1, the generic PSA was s...
To estimate power plant reliability, a probabilistic safety assessment might combine failure data fr...
To assess the risk of nuclear power plant operation and to determine the risk impact of digital syst...
Analyses were performed of the safety-related performance of the reactor protection system (RPS) at ...
This master thesis investigates definitions and classifications of the common cause failure from var...
Focused attention about multi-unit probabilistic safety assessment (PSA) after the Fukushima Daiichi...
The main goal of that project was to carry out a feasibility study of a methodology devoted to evalu...
In this study, an alternative for the analysis of common cause failures (CCFs) is investigated. The ...
Currently, the risk analysis software SAPHIRE has implemented a common-cause failure (CCF) module to...
The conclusions presented in the STUK report series are those of the authors and do not necessarily ...
Data bases of five studies concerned with failure probabilities of diesel generator systems in nucle...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
Nuclear power plants are increasingly being equipped with digital I&C systems. Although some pro...
Common cause fault rates for diesel generators in nuclear power plants are estimated, using Licensee...
Internationally, probabilistic safety analyses (PSA) represent the state of the art not only in the ...
Based on PSA simulations from https://data.mendeley.com/datasets/4nmvpnst8h/1, the generic PSA was s...
To estimate power plant reliability, a probabilistic safety assessment might combine failure data fr...
To assess the risk of nuclear power plant operation and to determine the risk impact of digital syst...