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AC600非能动安全壳冷却系统的概率安全分析
引用本文:王建瑜 张康. AC600非能动安全壳冷却系统的概率安全分析[J]. 核动力工程, 1998, 19(2): 149-153,161
作者姓名:王建瑜 张康
作者单位:[1]中国核动力研究设计院 [2]上海交通大学
摘    要:AC600是我国改进型压水堆核电站,本文对其在概念设计阶段的非能动专设安全设施中的安全壳冷却系统进行了概率安全分析(PSA)。文中采用故障树技术,定旧计算出了系统的不可用度及置信区间,主要部件故障对不同度的贡献和各组成单元的重要度等,并将计算结果与国内外现有压水堆核电站进行了比较,经比较得出AC600采用非能动安全冷却系统,将能明显提高核电站的安全性,可靠性和经济性,由于它是一种新的设计,因此围绕

关 键 词:非能动 安全壳 冷却系统 概率安全分析 故障树

Probabilistic Safety Analysis of AC600 PassiveContainment Cooling System
Wang Jianyu Zen Xi. Probabilistic Safety Analysis of AC600 PassiveContainment Cooling System[J]. Nuclear Power Engineering, 1998, 19(2): 149-153,161
Authors:Wang Jianyu Zen Xi
Abstract:This paper presents the probabilistic safety analysis(PSA)of containment cooling system in passive special safety facility for Chinese advanced PWRs of nuclear power plants AC600.The unavailability of the system,contribution of main parts fault to the unavailability and the key importance of each component are calculated by fault tree analysis technology.Comparing the results of the several existed PWRs at home and abroad,it can be concluded that passive containment cooling system of AC600 has a considerable improvement in terms of safety,reliability and economics.As a new design,it has a lot of topics to study further.
Keywords:Passive containment cooling system Probabilistic safety analysis Fault tree Unavailability
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