摘要
基于最佳估算程序TRACE,对大功率非能动核电厂冷却剂系统和非能动堆芯冷却系统进行了建模分析,得到了自动泄压系统(ADS)阀门误启动事故下,一回路压力、破口流量、一回路水装量等参数的瞬态变化,并以此为基准工况,根据电厂实践经验,选取泵延迟工况和阀门半开工况进行敏感性分析计算,将计算结果与基准工况进行了比较与分析.结果表明:虽然不同的工况可能造成一回路水装量低于基准工况,但最小的一回路水装量仍未低于限值,堆芯始终没有裸露,大功率非能动核电厂的非能动专设安全设施能有效对一回路进行冷却和降压,防止堆芯过热,验证了大功率非能动核电厂发生自动卸压系统误启动事故后的安全性.
Based on the best estimate program TRACE,the reactor coolant system and the passive core cooling system of high power passive nuclear power plant were modeled and analyzed.Some transient parameters of automatic depressurization system (ADS) inadvertent actuation accident were obtained,including system pressure,break discharge,system inventory,etc.Taking this as the reference condition,according to the practical experience of the power plant,the pump delay condition and the valve half-opening condition are selected for sensitivity analysis.The results were compared with the results generated by reference condition,and the differences between them were discussed.Although different working conditions may cause the RCS inventory to be lower than the reference condition,the minimum RCS inventory is still above the limit,and the core is never exposed.It is proved that the passive safety system of high power passive nuclear power plant can effectively reduce the temperature and pressure of the primary loop and also can prevent core overheating.The safety of high power passive nuclear power plant during the accident caused by inadvertent actuation of ADS was verified.
作者
庄少欣
孙微
刘宇生
靖剑平
安婕铷
ZHUANG Shaoxin;SUN Wei;LIU Yusheng;JING Jianping;AN Jieru(Nuclear and Radiation Safety Center,Beijing 100082,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2019年第4期588-594,共7页
Nuclear Science and Engineering
基金
国家科技重大专项CAP1400核安全监管重要试验验证资助(2015ZX06002007-001)
关键词
TRACE
自动泄压系统
非能动核电厂
TRACE
Automatic depressurization system
Passive nuclear power plant
