论文部分内容阅读
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。
AC600 is China’s improved PWR nuclear power plant. In this paper, we conduct a probabilistic safety analysis (PSA) of the containment cooling system in the passive safety equipment in the conceptual design stage. In this paper, the fault tree technique is used to quantitatively calculate the unavailability of the system and its confidence interval, the contribution of failure of main components to unavailability and the importance of each component. The results are compared with the existing PWR Nuclear power plants were compared. Comparing the AC600 with passive containment cooling system, it will be able to significantly improve the safety, reliability and economy of the nuclear power plant. Since it is a new design, many issues need to be further studied around the implementation of the system .