三门核电厂稳压器安全阀误开启事故研究Accident Analysis for Inadvertent Opening of Pressurizer Safety Valve in Sanmen NPP
陈杰,唐钢,邵舸,佟立丽
摘要(Abstract):
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。
关键词(KeyWords): 稳压器安全阀;事故分析;LOCA
基金项目(Foundation):
作者(Author): 陈杰,唐钢,邵舸,佟立丽
参考文献(References):
- [1]Westinghouse Electric Co.LLC.AP1000design control document,Revision19[R].Westinghouse Electric Co.LLC.2011.
- [2]朱瑞安,臧希年,曹小一.稳压器汽腔小破口失水事故的模拟[J].核动力工程,1993,14(2):144-148.
- [3]Kamyab S,Nematollahi M.Performance evaluating of the AP1000 passive safety systems for mitigation of small break loss of coolant accident using risk assessment tool-II software[J].Nuclear Engineering and Design,2012,253:32-40.
- [4]Guimaraes A C F,Lapa C M F,Filho F F L Set al.Fuzzy uncertainty modeling applied to AP1000nuclear power plant LOCA[J].Annals of Nuclear Energy,2011,38(8):1775-1786.
- [5]陈耀东.AP1000小破口叠加重力注射失效严重事故分析[J].原子能科学技术,2010,44:242-247.
- [6]Wright R F.Simulated AP1000response to design basis small-break LOCA events in APEX-1000test facility[J].Nuclear Engineering and Design,2007,39(4):287-298.
- [7]Bessette D E,Marzo M D.Transition from depressurization to long term cooling in AP600scaled integral test facilities[J].Nuclear Engineering and Design,1999,188:331-344.
- [8]USNRC.Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,10 CFR50.46[R].Nuclear Regulatory Commission.1988.