先进堆非能动堆芯应急冷却系统试验研究  

Experimental Investigation of Passive Emergency Core Cooling System

作　　者：彭云康[1] 郑华[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第2期158-163,共6页Nuclear Power Engineering

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.

关 键 词：非能动 应急冷却系统 自动卸压系统 

分 类 号：TL345.1[核科学技术—核技术及应用]