AP1000核电厂自动泄压系统误启动事故计算

Calculation of Inadvertent Actuation Accident of Automatic Depressurization System for APl000 Nuclear Power Plant

  • 摘要: 基于最佳估算程序RELAP5/MOD3.3,对AP1000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,系统压力、破口流量、系统水装量等参数的瞬态变化,计算结果与西屋公司采用NOTRUMP程序的计算结果进行了比较与分析。结果表明:AP1000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AP1000发生ADS阀门误启动事故后的安全性。

     

    Abstract: Based on the best estimate program RELAP5/MOD3.3, the reactor coolant system and the passive core cooling system of AP1000 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. The result was compared with the result generated by NOTRUMP code from Westinghouse, and the difference between them was discussed. It is proved that the passive safety system of APl000 nuclear power plant can effectively lower the temperature and reduce the pressure of the primary loop, and also can prevent core overheating. The safety of AP1000 nuclear power plant during the accident caused by inadvertent actuation of ADS was verified.

     

/

返回文章
返回