Author:
Xie Haiyan,Yang Dong,Zhao Yunjie,Jiang Huiqing,Qu Mofeng
Publisher
Springer Science and Business Media LLC
Reference34 articles.
1. Chang S.H., Baek W.P. Understanding, predicting, and enhancing critical heat flux, in: 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10). Seoul, Korea. 2003.
2. Celata G.P., Mishima K., Zummo G. Critical heat flux prediction for saturated flow boiling of water in vertical tubes. International Journal of Heat and Mass Transfer. 2001, 44(22): 4323–4331.
3. Wang S.Y., Yang D., Xie B.B., et al. Experimental investigation on heat transfer characteristics of water in inclined downward tube of a supercritical pressure CFB boiler. Journal of Thermal Science. 2015, 24(5): 478–487.
4. Wu H.B, Liu Z.H., Liao H.Y., et al. The study on the heat transfer characteristics of oxygen fuel combustion boiler. Journal of Thermal Science. 2016, 25(5): 470–475.
5. Lombardi C., Mazzola A. A criterion based on independent parameters for distinguishing departure from nucleate boiling and dryout in water cooled systems. Revue Générale De Thermique, 1998, 37(1): 31–38.
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