Abstract

Typical probabilistic safety assessment (PSA) results were used to estimate the performance indicator (PI) thresholds of unplanned reactor scram (URS) and safety system unavailability (SSU) for Korean nuclear power plants (NPPs). The changes in core damage frequency (${\Delta}$CDFs) of $10^{-6}/yr$, $10^{-5}/yr$, and $10^{-4}/yr$ were adopted as the risk criteria in setting up the PI thresholds. The PI thresholds for the URS were estimated using information pertaining to the initiating event frequencies, the CDF, and the CDF contribution of each initiating event. The PI thresholds of the SSU were estimated using information on the unavailability, the Fussell-Vesely importance, and the CDF.

주제어

#performance indicator thresholds   #unplanned reactor scram   #safety system unavailability   #probabilistic safety assessment   #core damage frequency  

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1. 2011. "" Nuclear engineering and technology : an international journal of the Korean Nuclear Society, 43(2): 105~132  원문보기 상세보기