The GO-FLOW reliability analysis methodology - analysis of common cause failures with uncertainty

被引：49

作者：

Matsuoka, T ^{[1
]}

Kobayashi, M ^{[1
]}

机构：

[1] Minist Transport, Ship Res Inst, Tokyo, Japan

来源：

NUCLEAR ENGINEERING AND DESIGN | 1997年 / 175卷 / 03期

关键词：

D O I：

10.1016/S0029-5493(97)00038-1

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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. (C) 1997 Elsevier Science S.A.

引用

页码：205 / 214

页数：10

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