郝老迷.沸腾传热和气液两相流动[M].哈尔滨工程大学出版社,2015.

张玉相,席炎炎,庞铮铮,李伟才,周跃民,赵华.CHF关系式开发与DNBR限值确定方法研究[J].核动力工程,2016(05).

熊万玉,王飞,肖泽军,卢冬华.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(04).

柴国旱,王小海,陈召林,陶书生.对临界热流密度计算关系式FC-2000的审评[J].核动力工程,2003(S2).

Marcinkiewicz Krzysztof,Wieckhorst Ole,Macián-Juan Rafael,Rehm Markus,Pohl Peter.Recurrent neural network-based prediction of critical heat flux in rod bundles with non-uniform axial power shape[J].Nuclear Engineering and Design,2022.

Pang Bo,Feng Simin,Yin Yuan.Development of a dimensionless rod-bundle CHF correlation based on stepwise regression method, Part II: determination of correction factors accounting for the effect of unheated guide tube and non-uniform axial heat flux profile[J].Annals of Nuclear Energy,2022.

Liu Wei,Peng Shinian,Jiang Guangming,Liu Yu.Development and assessment of a new CHF mechanistic model for subcooled and low quality flow boiling[J].International Journal of Heat and Mass Transfer,2021.

Wei Liu,Shinian Peng,Guangming Jiang,Yu Liu,Sijia Du,Yu Zhang,Jian Deng.Development and assessment of a new rod-bundle CHF correlation for China fuel assemblies[J].Annals of Nuclear Energy,2020.

M. Ferrouk,S. Aissani,F. D’Auria,A. DelNevo,A. Bousbia Salah.Assessment of 12 CHF prediction methods, for an axially non-uniform heat flux distribution, with the RELAP5 computer code[J].Nuclear Engineering and Design,2008.

D.C. Groeneveld,J.Q. Shan,A.Z. Vasić,L.K.H. Leung,A. Durmayaz,J. Yang,S.C. Cheng,A. Tanase.The 2006 CHF look-up table[J].Nuclear Engineering and Design,2007.

Kyu-Hyun Han,Dae-Hyun Hwang,Soon Heung Chang.Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes[J].Nuclear engineering and design,2006.

Se-Young Chun,Sang-Ki Moon,Won-Pil Baek,Moon-Ki Chung,Masanori Aritomi.An Experimental Study of Critical Heat Flux in Non-uniformly Heated Vertical Annulus under Low Flow Conditions[J].Journal of Mechanical Science and Technology,2003.

Dae-Hyun Hwang,Cheol Park,Sung-Quun Zee.A phenomenological approach to correcting DNB-type critical heat flux for non-uniform axial power shapes[J].International Journal of Heat and Mass Transfer,2001.

Tae Hyun Chun,Won Pil Baek,Soon Heung Chang.An integral equation model for critical heat flux at subcooled and low quality flow boiling[J].Nuclear Engineering and Design,2000.

Min Lee.A critical heat flux approach for square rod bundles using the 1995 Groeneveld CHF table and bundle data of heat transfer research facility[J].Nuclear Engineering and Design,2000(3).

D.C. Groeneveld,L.K.H. Leung,P.L. Kirillov,V.P. Bobkov,I.P. Smogalev,V.N. Vinogradov,X.C. Huang,E. Royer.The 1995 look-up table for critical heat flux in tubes[J].Nuclear Engineering and Design,1996(1).

D. C. Groeneveld,S. C. Cheng,T. Doan.1986 AECL-UO Critical Heat Flux Lookup Table[J].Heat Transfer Engineering,1986(1-2).

V. N. Smolin,V. K. Polyakov.COOLANT BOILING CRISIS IN ROD ASSEMBLIES[J].International Heat Transfer Conference 6,1978.

Tong L.S..Prediction of departure from nucleate boiling for an axially non-uniform heat flux distribution[J].Journal of Nuclear Energy,1967(3).