Survey of seismic fragilities used in PRA studies of nuclear power plants

被引:25
|
作者
Park, YJ
Hofmayer, CH
Chokshi, NC
机构
[1] Brookhaven Natl Lab, Dept Adv Technol, Upton, NY 11973 USA
[2] US Nucl Regulatory Commiss, Washington, DC 20555 USA
关键词
PRA; seismic fragilities; nuclear power plants;
D O I
10.1016/S0951-8320(98)00019-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In recent years, seismic PRA studies have been performed on a large number of nuclear power plants in the USA. This paper presents a summary of a survey on fragility databases and the range of evaluated fragility values of various equipment categories based on past PRAs. The survey includes the use of experience data, the interpretations of available test data, and the quantification of uncertainties. The surveyed fragility databases are limited to data available in the public domain such as NUREG reports, conference proceedings and other publicly available reports. The extent of the availability of data as well as limitations are studied and tabulated for various equipment categories. The survey of the fragility values in past PRA studies includes not only the best estimate values, but also the dominant failure modes and the estimated uncertainty levels for each equipment category. The engineering judgments employed in estimating the uncertainty in the fragility values are also studied. This paper provides a perspective on the seismic fragility evaluation procedures for equipment in order to clearly identify the engineering analysis and judgment used in past seismic PRA studies. (C) 1998 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:185 / 195
页数:11
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