CPR1000核电厂SGTR事故长期阶段的分析研究  

Long Term Optimization Analysis of Steam Generator Tube Rupture Accident for CPR1000

作　　者：鲍杰[1] 崔军 付浩 王一鸣 郑继业[1] Boo Jie;Cui Jun;Fu Hao;Wang Yiming;Zheng Jiye(Nuclear and Radiation Safety Center,MEP,Beijing 100082,China;China Nuclear Power Technology Research Institute,Shenzhen 518031,China)

机构地区：[1]环境保护部核与辐射安全中心,北京100082 [2]中广核研究院有限公司,深圳518031

出　　处：《核安全》2018年第4期10-16,共7页Nuclear Safety

摘　　要：对于蒸汽发生器传热管破裂事故,现有的分析主要是计算对于环境的释放量,并分析至一、二回路压力平衡,而未对冷却至安全停堆状态进行研究。SGTR长期分析采用CATHARE程序以原有瞬态分析为基础,将分析拓展至安全停堆状态,并额外地考虑丧失厂外电和一些非安全级系统不可用情况下的事故处理策略。分析结果表明:对于我国的CPR1000系列堆型,与SGTR短期阶段不同,在事故长期阶段的分析中对事故的缓解必须考虑非安全级系统或设备的投入,这就与设计基准事故分析的保守性要求不符。本文为此对我国CPR1000系列核电厂提出管理建议。For the steam generator tube rupture （SGTR） accident, the existing analysis is mainly to calcu- late the release amount of radiation to the environment, only to analyze the pressure balance of the primary and secondary loop, but not to the further cooling to the safe shutdown state. SGTR long term analysis u- ses the CATHARE code to extend the analysis to safe shutdown state based on the transient analysis. And additionally, the loss of offsite power （LOOP） and some non - safety system availability are considered in case of accident treatment strategies. The results show that： for the CPR1000 series plants in China, dif- ferent from the short-term stage of SGTR, it is necessary to consider the effects of the non - safety system or equipment in the analysis of the long term accident, which is inconsistent with the conservative require- ments of the design basis accident analysis. Accordingly, some management suggestions for CPR1000 se- ries nuclear power plants in China are put forward to strengthen the weak link.

关 键 词：SGTR 事故分析 长期阶段 

分 类 号：TL364.4[核科学技术—核技术及应用]