Experimental and Analytical Studies for Seismic Behavior of Residual Heat Removal System in Nuclear Power Plants
Date Issued
2015
Date
2015
Author(s)
Chang, Wen-Chieh
Abstract
Seismic probabilistic risk assessment (SPRA) has been widely used to compute the frequencies of core damage and release of radiation of nuclear power plant (NNP).In 2011, Huang, Whittaker, and Luco published a new SPRA methodology, different from existing SPRA, including nonlinear response-history analysis of structure to estimate seismic demands for component and the component fragility curves are functions of component response parameters. In the study presented in this thesis, the methodologies of developing ground-motion-based and response-based component fragility curves with numerical models are presented. A residual heat removal (RHR) piping system which contributes significantly to the seismic risk of a sample NPP has been analyzed experimentally and numerically. Then, the numerical model based on experimental result is used to develop a response-based fragility curve for the system. Comparing to the ground-motion-based component fragility analysis result, the response-based fragility analysis result is more conservative and reliable, so recommendation is using response-based fragility curves in seismic probabilistic risk assessment.
Subjects
seismic probabilistic risk assessment
nonlinear response-history analysis
residual heat removal piping system
component fragility analysis
Type
thesis
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