Study of CHF under Non-uniform Heating Condition in Rectangular Channel

被引：0
|
作者：
Wang W. [1 ]
Huang H.-J. [1 ]
Chen B.-W. [1 ]
Chen X. [1 ]
机构：
[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
来源：
| 1600年 / Atomic Energy Press卷 / 51期
关键词：
Critical heat flux; F factor; Non-uniform heating; Rectangular channel;
D O I：
10.7538/yzk.2017.51.07.1195
中图分类号：
学科分类号：
摘要：
Aimed at the existing correlations of CHF (critical heat flux) under the condition of uniform heating, such as Sudo93, Sudo96, Knoebel and W3 formulas, the non-uniform heating condition was considered, and the correlation of CHF was generalized to rectangular channel condition and revised by the method of length of boiling and F factor method. Aimed at the actual operating case of China Advanced Research Reactor (CARR), the revised calculation results were compared with the experimental values of CARR. The results show that the results of Sudo series formulas which are revised by F factor are in good agreement with the experimental values, so they can better predict the CHF phenomenon of CARR. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：1195 / 1201
页数：6
相关论文
共 11 条
  • [1] Mirshak S., Durant W.S., Towell R.H., Heat Flux at Burnout, DP-355, (1959)
  • [2] Gambill W.R., Mochizuki T., Advanced Neutron Source Design: Burnout Heat Flux Correlation Development, (1988)
  • [3] Hisashi U., Kitajima T., Hirayama M., Et al., Critical heat flux in non-uniformly heated tube under low-pressure and low-mass-flux condition, heat transfer, Asian Research, 35, 1, pp. 47-60, (2006)
  • [4] Katto Y., General features of CHF of forced cenvection boiling in uniformly heated rectangular channels, Int J Heat Mass Transfer, 24, 8, pp. 1413-1419, (1981)
  • [5] Sudo Y., A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors, Journal of Heat Transfer, 115, pp. 426-435, (1993)
  • [6] Sudo Y., Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0.1 to 14 Mpa, Heat Transfer, 118, pp. 680-688, (1996)
  • [7] Tong L.S., Prediction of departure from nuclear boiling for an axially non-uniform heat flux distribution, Journal of Nuclear Energy, 21, pp. 241-248, (1967)
  • [8] Tian W., Qiu S., Guo Y., Et al., The calculation of mass flux distribution of CARR, Chinese Journal of Nuclear Science and Engineering, 25, 2, pp. 137-142, (2005)
  • [9] Tian W., Qiu S., Guo Y., Et al., Development of steady thermal-hydraulic analysis code for China Advanced Research Reactor, Atomic Energy Science and Technology, 40, 1, pp. 51-56, (2006)
  • [10] Lu D., Bai X., Huang Y., Et al., Study on CHF in thin rectangular channels and evaluation of its empirical correlations, Chinese Journal of Nuclear Science and Engineering, 24, 3, pp. 242-248, (2004)
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