【摘要】 秦山二期核电厂是两环路电功率为 ６００ ＭＷ的核电厂，而已进行过概率安全分析的广东大亚湾核电厂则为三环路９００ＭＷ核电厂。本文以去掉一个环路的９００ＭＷ三环路核电厂为参考电厂来进行两环路核电厂概率安全分析（ＰＳＡ）。分析结果指出：１）只要满足确定论安全审查，两环路核电厂的概率安全特性不亚于三环路核电厂的概率安全特性；２）参考的两环路核电厂堆熔频率为２．４２×１０－５／（堆年）；３）参考的两环路核电厂严重事故的支配性初因依次为失水事故（ＬＯＣＡ）和丧失热阱。本研究对两环路核电厂设计、建造和运行提供了有益的参考。更多还原

【Abstract】 Qinshan second phase nuclear power plant (NPP) is a two-loop NPP with the electric power of 600 MW while Guangdong nuclear power plant whose probabilistic safety analysis (PSA) has been completed is a three-loop NPP with the electric power of 900 MW. The PSA for the two-loop nuclear power plant was performed on the basis of the Guangdong nuclear power plant simplified by removing one from three loops as a reference NPP. The most important results of the study include that: 1) the probabilistic safety feature of the two-loop nuclear power plant is equivalent to that of the three-loop nuclear power plant; 2) the core melt frequency of the reference NPP is 2. 42 × 10-5 per year per reactor ; 3) the loss of coolant accident (LOCA) and loss of heat sink are the first and second initiating events respectively which could cause serious accidents. This study provides profitable insights for designing, constructing and operating of the two-loop nuclear power plant.更多还原