Critical Heat Flux(CHF)Correlations for Subcooled Water Flow Boiling at High Pressure and High Heat Flux

作     者：LIU Ping GUO Yusheng DING Wenlong TANG Mingyun SONG Yuntao PENG Xuebing JI Jiadong CHEN Qinghua MAO Xin LIU Ping;GUO Yusheng;DING Wenlong;TANG Mingyun;SONG Yuntao;PENG Xuebing;JI Jiadong;CHEN Qinghua;MAO Xin

作者机构：State Key Laboratory of Mining Response and Disaster Prevention and Control in Deep Coal MinesAnhui University of Science and TechnologyHuainan 232001China School of Mechanical EngineeringAnhui University of Science and TechnologyHuainan 232001China Anhui Key Laboratory of Mine Intelligent Equipment and TechnologyAnhui University of Science and TechnologyHuainan 232001China Institute of Plasma PhysicsChinese Academy of SciencesHefei 230031China School of Mining and Safety EngineeringAnhui University of Science and TechnologyHuainan 232001China 

出 版 物：《Journal of Thermal Science》 (热科学学报（英文版）)

年 卷 期：2021年第30卷第1期

页      面：279-293页

核心收录：

学科分类：08[工学] 0827[工学-核科学与技术] 082701[工学-核能科学与工程] 0805[工学-材料科学与工程（可授工学、理学学位）] 0702[理学-物理学] 

基　　金：supported by National Natural Science Foundation of China(Grant No.11805005) National Natural Science Foundation of China(Grant No.11705234) Visiting and Research Project at Home and Abroad for Outstanding Youth Talents of Anhui Province University(Grant No.gxgwfx2018024) National Magnetic Confinement Fusion Science Program of China(Grant No.2014GB101001) Key University Science Research Project of Anhui Province(Grant No.KJ2018A0080) Key project of excellent young talent support program of Anhui Province of China(Grant No.gxyq ZD2016087) Provincial Natural Science Foundation of Anhui(Grant No.1608085ME89)。 

主　　题：reactor divertor correlations subcooled water flow boiling critical heat flux(CHF) high heat flux high pressure 

摘      要：The subcooled water flow boiling is beneficial for removing the high heat flux from the divertor in the fusion reactor,for which an accurate critical heat flux(CHF)correlation is necessary.Up to now,there are many CHF correlations mentioned for subcooled water flow boiling in the open literatures.However,the CHF correlations’accuracies for the prediction of subcooled water flow boiling are not satisfactory at high heat flux and high pressure for reactor divertor.The present paper compiled 1356 CHF experimental data points from 15 independent open literatures and evaluated 10 existing CHF correlations in subcooled water flow boiling.From the evaluation,the W-2 CHF correlation performs best for the experimental CHF data in all existing critical heat flux correlations.However,the predicted mean absolute error(MAE)of the W-2 correlation is not very ideal for all database and the MAE of the W-2 correlation is from 30%to 50%for some database.In order to enhance the CHF prediction accuracy in subcooled water flow boiling at high heat flux and high pressure,the present paper developed a new CHF correlation.Compared with other existing CHF correlations,the new CHF correlation greatly enhances the prediction accuracy over a broad range of pressures and heat fluxes which are desired in the cooling of high heat flux devices,such as those in the fusion reactor divertor.The validation results show that the new correlation has a MAE of 10.05%and a root mean squared error(RMSE)of 16.61%,predicting 68.1%of the entire database within±10%and 81.5%within±15%.The MAE of the new CHF correlation is 7.4%less than that of the best existing one(W-2 correlation),further confirming its superior prediction accuracy and reliability.Besides,the new CHF correlation works well not only for a uniform power profile but also for a non-uniform power profile in subcooled water flow boiling at high pressure and high heat flux.