DVI管小破口失水事故实验研究  

Experimental Investigation on Small Break Loss of Coolant Accident for Direct Vessel Injection Line

作　　者：彭传新[1] 张妍[1] 黄志刚[1] 昝元锋 卓文彬[1] 闫晓[1] 

机构地区：[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,四川成都610041

出　　处：《原子能科学技术》2016年第10期1787-1792,共6页Atomic Energy Science and Technology

基　　金：国家杰出青年科学基金资助项目(11325526);863计划资助项目(2012AA050906)

摘　　要：在模块化小型反应堆非能动安全系统综合模拟实验装置上进行了压力容器直接注入(DVI)管小破口失水事故实验,研究了DVI管小破口失水事故过程中的热工水力现象和非能动安全系统运行特性。研究结果表明:模块化小型反应堆DVI管小破口失水事故中,非能动安全系统可对堆芯进行注水,有效导出堆芯衰变热量,保护堆芯安全。The small break loss of coolant accident（SBLOCA）experiment for direct vessel injection（DVI）line,which investigated the thermal-hydraulic phenomena and the performances of passive safety system during the accident,was performed on the passive safety system test facility for small modular reactor.The experimental results show that the passive safety system of small modular reactor can provide effective coolant injection,successful removal of core residual heat under the DVI line SBLOCA and protection to reactor core safety.

关 键 词：小破口失水事故 DVI管 非能动安全系统 

分 类 号：TK124[动力工程及工程热物理—工程热物理]