高压工况下圆管内垂直向上流动沸腾CHF关系式比较研究  

Comparative Study of CHF Correlations in Upflow Boiling Vertical Round Tube under High Pressure

作　　者：刘伟[1] 彭诗念[1] 江光明[1] 刘余[1] 沈才芬[1] 单建强[2] Liu Wei;Peng Shinian;Jiang Guangming;Liu Yu;Shen Caifen;Shan Jianqiang(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;School of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an,710049,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213 [2]西安交通大学核科学与技术学院,西安710049

出　　处：《核动力工程》2019年第1期152-155,共4页Nuclear Power Engineering

摘　　要：基于15 MPa至临界压力的圆管内垂直向上流动沸腾临界热流密度(CHF)实验数据,筛选出Katto、Bowring、Hall-Mudawar、Alekseev关系式以及CHF查询表(LUT-2006)进行比较研究,通过对预测值与实验值的误差分析,评价了各个关系式的适用性,得到了15 MPa至临界压力区间内CHF随压力的变化趋势。本研究对高压工况(≥15 MPa),尤其是接近临界区域的CHF预测具有指导意义。Based on the experiment database of upflow boiling in the vertical round tube from 15 MPa to critical pressure of water, the Katto, Bowring, Hall-Mudawar, Alekseev correlation and LUT-2006 are comparatively studied. With the error analysis of the CHF correlations to the experiment database, the applicability of these correlations is estimated and the parametric trends of CHF with pressure from 15 MPa to critical pressure are proposed. Findings of this study have a positive effect on further development of CHF prediction method, especially under high and critical pressure area.

关 键 词：高压工况 圆管 流动沸腾 CHF关系式 

分 类 号：TL334[核科学技术—核技术及应用]