AP1000仿真系统失水事故的定性分析

Qualitative Analysis on SB-LOCA of AP1000 Simulation Model

在低碳背景下,国家对核电的投入正在逐步加大,核反应堆的安全性也越来越引起人们的重视。本文采用RELAP5/MOD3.4软件以AP1000主冷却剂系统为原型进行仿真建模,定性分析了AP1000小破口失水事故(SB-LOCA)的发生过程,并与AP1000安全分析报告(SAR)中的SB-LOCA做了比较,为进一步仿真建模做铺垫。

Under the background of low carbon,the government increases the investment of nuclear power industry gradually,and people attach more importance to the nuclear reactor safety.Taking the primary coolant system of AP1000 as a prototype,using the software RELAP5/MOD3.4,a simulation model was established.Based on this,the process of the small break loss of coolant accident(SB-LOCA) was analyzed qualitatively;and the result was compared with the SB-LOCA in the safety analysis report(SAR) of AP1000.The analysis p...