CAJ | 학술논문

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。
가설AP1000핵전엄발생유사복도핵사고적초인사건，이용RELAP5/MOD3.3정서대사고조기적일、이회로계통화비능동안전계통진행모의계산，득도료반응퇴냉각제계통압력、퇴심냉각제온도、비능동안전계통류량등중요삼수적순태변화。분석표명：재비능동여열배출계통완호적정황하，반응퇴계통능순리진입열정퇴상태；여과비능동여열배출계통1근환열관발생쌍단단렬，칙반응퇴계통장회재5h내발생엄중사고。
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 .