摘要
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。
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.
出处
《核科学与工程》
CSCD
北大核心
2015年第1期163-168,共6页
Nuclear Science and Engineering
