Seismic Probabilistic Risk Assessment of Nuclear Power Plants Using Response-Based Fragility Functions and Seismic Behavior of Residual Heat Removal System
Date Issued
2014
Date
2014
Author(s)
Yu, Ching-Ching
Abstract
Seismic probabilistic risk assessment (SPRA) has been widely used to compute the frequencies of core damage and release of radiation of a nuclear power plant (NPP). In 2011, Huang, Whittaker, and Luco published a SPRA methodology with the following characteristics different from the widely used Zion method: (a) seismic fragility curves are defined as a function of structural response parameters; (b) nonlinear response-history analysis is used to estimate seismic demands for components of NPPs; (c) generating a large number of simulations through statistical manipulation of a relatively small number of structural analyses; (d) Monte Carlo simulation is used to determine damage states of components.
In the study presented in this paper, the seismic risk of a sample NPP was evaluated using the methodology published by Huang, Whittaker, and Luco, and the pros and cons of the methodology will be discussed. The seismic risk studied herein was defined as the annual frequency of unacceptable performance of a sample accident sequence for the
sample NPP. Variations in the strength of structural and non-structural components,damping and soil properties are directly considered in the numerical models used in response-history analysis. The procedure to determine the minimum number of structural analyses was also presented in this study.
In this study, the seismic performance of a critical piping system in the sample NPP was evaluated numerically and experimentally. The results will be used to establish the
response-based fragility curve for the piping system in the next stage of this study.
Subjects
地震機率式風險評估
蒙地卡羅模擬法
餘熱移除系統
Type
thesis
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