小型堆破口失水事故初步研究

为验证中国广核集团小型堆方案设计，尤其是其中非能动安全注入系统的初步设计，基于RELAP/SCDAPSIM程序，建立了小型堆的一、二回路系统和非能动安全注入系统模型，模拟计算了冷管段0.04 m等效直径破口、冷管段0.2 m等效直径破口、直接注入管道双端断裂、自动卸压系统误启动等LOCA工况。计算结果表明，一回路可实现有效的冷却和降压，堆芯不会过热，验证了其非能动安全注入系统的设计合理性和反应堆系统的安全性。

Study on Break LOCA of Small Reactor

To verify the scheme design of small reactor for China General Nuclear Power Group,especially the scheme design of passive safety injection system,the primary loop,the second loop and the passive core cooling system were modeled based on the RELAP/SCDAPSIM code.The break loss of coolant accidents (LOCA ) including equivalent diameter 0.04 m cold leg break,equivalent diameter 0.2 m cold leg break, double-ended direct injection line break,and inadvertent ADS actuation were simulated and calculated.The results show that the primary loop can achieve effective cooling and depressurization,and the core does not become overheat.The safety of small reactor and the rationality of the passive core cooling system are verified.