CAJ | 학술논문

稳压器安全阀用于核电站一回路系统和设备的超压保护，如果发生故障卡开，将造成冷却剂丧失事故(LOCA)。本文使用机理性分析程序对三门核电厂1号机组进行建模，并对稳压器安全阀误开启导致的 LOCA 事故进行模拟分析，研究在稳压器水位较高的情况下，非能动安全设施对 LOCA 事故的响应情况。之后，为验证三门核电站对类似三哩岛事故的应对能力，假设丧失给水叠加稳压器安全阀卡开事故并进行相应事故分析。通过以上两个事故的分析表明，三门核电厂的非能动安全设计能够应对稳压器安全阀故障造成的 LOCA 事故，保证对一回路补水，不会造成非常严重的事故后果。
은압기안전벌용우핵전참일회로계통화설비적초압보호，여과발생고장잡개，장조성냉각제상실사고(LOCA)。본문사용궤이성분석정서대삼문핵전엄1호궤조진행건모，병대은압기안전벌오개계도치적 LOCA 사고진행모의분석，연구재은압기수위교고적정황하，비능동안전설시대 LOCA 사고적향응정황。지후，위험증삼문핵전참대유사삼리도사고적응대능력，가설상실급수첩가은압기안전벌잡개사고병진행상응사고분석。통과이상량개사고적분석표명，삼문핵전엄적비능동안전설계능구응대은압기안전벌고장조성적 LOCA 사고，보증대일회로보수，불회조성비상엄중적사고후과。
Pressurizer safety valves are used as over-pressure protection devices for the primary system component in nuclear power plant.A loss of coolant accident (LOCA) will be caused by inadvertent opening of the pressurizer safety valve.The model of Sanmen Unit 1 is developed by mechanical analytical code in this article to analyze the LOCA caused by inadvertent opening of one pressurizer safety valve,and the response of passive safety-related facilities to LOCA with a relatively high pressurizer water level is investigated.Besides,in order to verify the capacity of Sanmen in respond to the accident such as Three Miles Island accident,loss of feedwater with inadvertent opening of one pressurized safety valve is also analyzed.The results show that the passive safety design in Sanmen can mitigate the LOCA caused by inadvertent opening of one pressurizer safety valve to ensure the water makeup for the primary system,which will not result in serious consequence.