压力容器外部冷却技术研究进展及建议  

Studyand Suggestions on the External Reactor Vessel Cooling

作　　者：邓江明 陈薇 钟达文[3] 申中祥[1] 炊晓东[1] 张兆虎 DENG Jiang-ming;CHEN Wei;ZHONG Da-wen;SHEN Zhong-xiang;CHUI Xiao-dong;ZHANG Zhao-hu(Research Institute of Nuclear Power Operation, Wuhan, Hubei Prov. 430223,China;China Nuclear Energy Development Center, Beijing 100045, China;North China Electric Power University, Beijing 102206, China)

机构地区：[1]核动力运行研究所,湖北武汉430223 [2]中国核电发展中心,北京100045 [3]华北电力大学,北京102206

出　　处：《中国核电》2019年第2期152-157,共6页China Nuclear Power

摘　　要：2011年福岛核事故再次让人们意识到核泄漏的严重性,压力容器外部冷却技术作为压水堆严重事故下堆内熔融物滞留的关键技术,再次成为国际核能领域的研究热点。压力容器外部冷却技术通过非能动方式向反应堆腔室充水,使压力容器半球形封头淹没并进行沸腾冷却,从而保持压力容器的完整性,避免核泄漏的发生。本文总结了国际压力容器外部冷却技术的研究进展,详细分析了试验研究的三个阶段,简要介绍了ERVC的应用情况,指出了压力容器外部冷却技术性能提高的三种途径。The Fukushima nuclear accident in 2011 made people aware of the severity of the nuclear leakage again, the external reactor vessel cooling(ERVC), as the key technology for the in vessel retention(IVR) of the core melt under serious accident of PWR, once again became the hot spot in the international nuclear energy field. The external reactor vessel cooling involves flooding the reactor cavity to submerge the reactor vessel to cool the core debris by boiling heat transfer, which maintains the integrity of the pressure vessel and avoids the occurrence of nuclear leakage. This paper summarizes the research progress of external reactor vessel cooling,analyzes the three stages of experimental research in detail, and points out three ways to improve the performance of ERVC.

关 键 词：严重事故 外部冷却 沸腾换热 研究进展 

分 类 号：TM623[电气工程—电力系统及自动化]