Abstract
Common cause failures (CCFs) have long been recognized as an important issue in the probabilistic safety assessment (PSA) for nuclear power plants. Uncertainty ranges of system failure probabilities are important information for the evaluation of system reliability. The function of CCF analysis together with uncertainty analysis has been provided to the GO-FLOW methodology. Overview of the GO-FLOW methodology, the method to treat the CCFs in the GO-FLOW, the procedure of CCF analysis together with uncertainty are described. As the sample system, PWR auxiliary feedwater system has been taken and an analysis has been performed by the proposed analysis framework.
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