A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants

被引:134
作者
Aldemir, Tunc [1 ]
机构
[1] Ohio State Univ, Dept Mech & Aerosp Engn, Scott Lab 427, Columbus, OH 43210 USA
关键词
Probabilistic safety assessment; Probabilistic risk assessment; Epistemic uncertainties; REACTOR DYNAMICS; RELIABILITY-ANALYSIS; FAILURE ANALYSIS; RISK-ASSESSMENT; MONTE-CARLO; SYSTEMS; GENERATION; TREES; FLOW; PSA;
D O I
10.1016/j.anucene.2012.08.001
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
Dynamic methodologies for probabilistic safety assessment (PSA) are defined as those which use a time-dependent phenomenological model of system evolution along with its stochastic behavior to account for possible dependencies between failure events. Over the past 30 years, numerous concerns have been raised in the literature regarding the capability of the traditional static modeling approaches such as the event-tree/fault-tree methodology to adequately account for the impact of process/hardware/software/firmware/human interactions on the stochastic system behavior. A survey of the types of dynamic PSA methodologies proposed to date is presented, as well as a brief summary of an example application for the PSA modeling of a digital feedwater control system of an operating pressurized water reactor. The use of dynamic methodologies for PSA modeling of passive components and phenomenological uncertainties are also discussed. (C) 2012 Elsevier Ltd. All rights reserved.
引用
收藏
页码:113 / 124
页数:12
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