福岛条件下AP1000核电厂事故前期研究

Study on Early Phase of AP1000 Accident Under Fukushima Condition

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5h内发生严重事故。

Simulation calculations of AP1000 nuclear power plant consisting of the pri-mary 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 shutdow n 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 .