参考文献/References:
[1] 卢冬雪,白雪松,黄彦平,等.扁矩形通道CHF试验研究及其CHF关系式的分析评估[J].核科学与工程,2004,24(3):242-248.
LU Dong-hua,BAI Xue-song,HUANG Yan-ping,et al.Study on CHF in thin rectangular channels and evaluation of its empirical correlations[J].Chinese Journal of Nuclear Science and Engineering,2004,24(3):242-248.
[2] 秋穗正,张维忠,廖义香,等.液钠沸腾两相流流型与临界热流密度(CHF)机理实验研究[J].核科学与工程,2001,21(3):232-237.
QIU Sui-zheng,ZHANG Wei-zhong,LIAO Yi-xiang,et al. Experimental Study on Two-phase Flow Pattern and Critical Heat Flux(CHF)Mechanism of Liquid Sodium Boiling[J].Chinese Journal of Nuclear Science and Engineering,
2001,21(3):232-237.
[3] 陈常念,韩吉田,邵 莉,等.R134a卧式螺旋管内流动沸腾CHF特性研究[J].核动力工程,2010,31(5):76-80.
CHEN Chang-nian,HAN Ji-tian,SHAO Li,et al. Study on Dry-out CHF Characteristics of R134Flow Boiling in Horizontal Helically-coiled Tubes[J].Nuclear Power Engineering, 2010,31(5):76-80.
[4] 罗小平,唐 杨.矩形微槽道饱和沸腾临界热流密度特性[J].低温与超导,2010,38(6):66-70.
LUO Xiao-ping,TANG Yang. Properties of saturated flow boiling critical heat flux through rectangular mico-channel[J].Cryo and Supercond,2010,38(6):66-70.
[5] 熊万玉,王 飞,肖泽军,等.矩形窄缝通道轴向非均匀加热临界热流密度实验研究[J].核动力工程,2007,28(4):34-38.
XIONG Wan-yu,WANG Fei,XIAO Ze-jun,et al.Test of Critical Heat Flux with Non-Uniform Axial Power Shapes in Rectangle Narrow Channel[J].Nuclear Power Engineering,2007, 28(4): 34-38.
[6] RODAY A P,JENSEN M K.Study of the critical heat flux condition with water and R123during flow boiling in microtubes[J].International Journal of Heat and Mass Transfer, 2009, 52:3250-3256.
[7] CHIRAG R Kharangate,ISSAM Mudawar,MOHAMMAD M Hasan. Experimental and theoretical study of critical heat flux in vertical up-flow with inlet vapor void[J]. International Journal of Heat and Mass Transfer,2011,50:360-374.