临界热流密度实验技术研究进展  

Investigation progress on the experimental technology of critical heat flux

作　　者：陈泽亮 黄潇立 吴达岭 桂南[1] 杨星团[1] 姜胜耀[1] 宫厚军[3] CHEN Zeliang;HUANG Xiaoli;WU Daling;GUI Nan;YANG Xingtuan;JIANG Shengyao;GONG Houjun(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China;Zhejiang Academy of Emergency Management Science and Technology,Hangzhou 310012,China;Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]清华大学核能与新能源研究院,北京100084 [2]浙江省应急管理科学研究院,浙江杭州310012 [3]中国核动力研究设计院,四川成都610213

出　　处：《实验技术与管理》2022年第8期10-16,共7页Experimental Technology and Management

基　　金：国防科技工业核动力技术创新中心项目(HDLCXZX-2020-HD-022)。

摘　　要：临界热流密度(CHF)是反应堆重要的限制性热工水力参数之一,它的大小直接影响了反应堆的安全性和经济性。由于CHF涉及沸腾、两相流等复杂的物理现象,因此通常采用实验的方式来获取。该文介绍了国内外临界热流密度相关的机理性实验和工程性实验研究工作,总结了实验技术相关方面的特点,可为反应堆热工水力学中CHF相关的实验研究提供技术参考。The critical heat flux(CHF) is one of the important key parameters of the thermal hydraulics of reactor engineering. Its value directly affects the safety and economy of the reactor. Because CHF involves complex physical phenomena such as the boiling and two-phase flow, it is usually obtained by experiment. This paper introduces the international experimental investigations on the mechanisms and engineering applications experiment related to the critical heat flux. Also, it summarizes the characteristics of experimental technology,which can provide technical reference for the experimental study of critical heat flux in reactors thermal hydraulics.

关 键 词：临界热流密度 实验技术 池沸腾 流动沸腾 

分 类 号：TL333[核科学技术—核技术及应用]