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，定量计算出了系统的不可用度及其置信区间、主要部件故障对不可用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采用非能动安全壳冷却系统，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，因此围绕系统的实施，还有许多课题需要深入研究。
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.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第2期149-153,161,共6页
Nuclear Power Engineering
关键词
非能动
安全壳
冷却系统
概率安全分析
故障树
Passive containment cooling system Probabilistic safety analysis Fault tree Unavailability
