福岛条件下AP1000核电厂事故前期研究

假设AP1000核电厂发生类似福岛核事故的初因事件，利用RELAP5/MOD3.3程序对事故早期的一、二回路系统和非能动安全系统进行模拟计算，得到了反应堆冷却剂系统压力、堆芯冷却剂温度、非能动安全系统流量等重要参数的瞬态变化。分析表明：在非能动余热排出系统完好的情况下，反应堆系统能顺利进入热停堆状态；如果非能动余热排出系统1根换热管发生双端断裂，则反应堆系统将会在5 h内发生严重事故。

Study on Early Phase of AP1000 Accident Under Fukushima Condition

Simulation calculations of AP1000 nuclear power plant consisting of the primary and secondary loop systems, and the passive safety systems with RELAP5/MOD3.3 code were performed under the assumption of Fukushima nuclear accident. Some key transient parameters including RCS pressure, core coolant temperature, and passive safety system flow were obtained. The analysis results show that the AP1000 reactor can reach hot shutdown status with the passive residual heat removal system (PRHRS) available; however the reactor will undergo severe accident in five hours with the assumption of double-ended rupture of one PRHRS tube.