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作者机构:Ohio State Univ Nucl Engn Program Scott Lab 427 Columbus OH 43102 USA Ohio State Univ Dept Comp Sci & Engn Dreese Labs 395 Columbus OH 43210 USA Ohio State Univ Dept Elect & Comp Engn Dreese Labs 320 Columbus OH 43210 USA US Nucl Regulatory Commiss Off Nucl Regulatory Res Washington DC 20555 USA
出 版 物:《NUCLEAR TECHNOLOGY》 (Nucl Technol)
年 卷 期:2009年第165卷第1期
页 面:53-95页
核心收录:
学科分类:08[工学] 0827[工学-核科学与技术]
基 金:U.S. Nuclear Regulatory Commission
主 题:Markov dynamic flowgraph methodology dynamic PRA
摘 要:There is an accelerating trend to upgrade and replace nuclear power plant analog instrumentation and control systems with digital systems. While various methodologies are available for the reliability modeling of these systems for plant probabilistic risk assessments, there is no benchmark system that can be used as the basis for methodology comparison. A system representative of the steam generator feedwater control systems in pressurized water reactors is proposed for such a comparison. Dynamic reliability modeling of the benchmark system for an example initiating event is illustrated using the Markov/cell-to-cell mapping technique and dynamic flowgraph methodologies.