摘要
对AC600全压堆芯补水箱补水实验装置进行了改造,研究了不同尺寸的冷段破口、不同的堆芯补水箱压力平衡管以及自动卸压系统对非能动堆芯应急冷却系统瞬态特性的影响;简要描述了实验过程及实验结果,为先进堆非能动堆芯应急冷却系统的设计提供了实验依据。
The AC600 CMT test facility was modified by Nuclear Power Institute of China (NPIC). The effect of different break size at cold leg, different pressure balance line and automatic depressurize system on transient behavior of passive emergency core cooling system was investigated on the modified test facility. The experiment process and experiment results were described in this paper.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2003年第2期158-163,共6页
Nuclear Power Engineering
关键词
非能动
应急冷却系统
自动卸压系统
Passive
Emergency core cooling system
Automatic depressurize system
