矩形通道轴向非均匀加热条件下的CHF研究
Study of CHF under Non-uniform Heating Condition in Rectangular Channel
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摘要: 针对已有的计算均匀加热条件下的临界热流密度(CHF)的关系式,如Sudo93、Sudo96、Knoebel公式以及W3公式,加以非均匀条件的考虑,推广到矩形通道工况下,并用计算非均匀加热条件的沸腾长度法和F因子法对其进行修正。针对中国先进研究堆(CARR)的实际运行工况,运用修正后的计算结果与CARR的实验值进行比较。结果表明,通过F因子修正后的Sudo系列公式计算结果与实验值符合良好,从而能够较好地预测CARR的CHF现象。Abstract: 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.
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Keywords:
- rectangular channel ,
- non-uniform heating ,
- critical heat flux ,
- F factor
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[1] 于平安. 核反应堆热工分析[M]. 3版. 上海:上海交通大学出版社,2002:36-41,168-171. [2] MIRSHAK S, DURANT W S, TOWELL R H. Heat flux at burnout, DP-355[R]. US: USAEC, 1959. [3] GAMBILL W R, MOCHIZUKI T. Advanced neutron source design: Burnout heat flux correlation development[R]. US: Oak Ridge National Laboratory, 1988. [4] 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[J]. Asian Research, 2006, 35(1): 47-60. [5] KATTO Y. General features of CHF of forced cenvection boiling in uniformly heated rectangular channels[J]. Int J Heat Mass Transfer, 1981, 24(8): 1413-1419. [6] SUDO Y. A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors[J]. Journal of Heat Transfer, 1993, 115: 426-435. [7] 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[J]. Heat Transfer, 1996, 118: 680-688. [8] TONG L S. Prediction of departure from nuclear boiling for an axially non-uniform heat flux distribution[J]. Journal of Nuclear Energy, 1967, 21: 241-248. [9] 田文喜,秋穗正,郭赟,等. 中国先进研究堆堆芯流量分配计算[J]. 核科学与工程,2005,25(2):137-142.TIAN Wenxi, QIU Suizheng, GUO Yun, et al. The calculation of mass flux distribution of CARR[J]. Chinese Journal of Nuclear Science and Engineering, 2005, 25(2): 137-142(in Chinese). [10] 田文喜,秋穗正,郭赟,等. 中国先进研究堆稳态热工水力计算程序开发[J]. 原子能科学技术,2006,40(1):51-56.TIAN Wenxi, QIU Suizheng, GUO Yun, et al. Development of steady thermal-hydraulic analysis code for China Advanced Research Reactor[J]. Atomic Energy Science and Technology, 2006, 40(1): 51-56(in Chinese). [11] 卢冬华,白雪松,黄彦平,等. 扁矩形通道CHF实验研究及其CHF关系式的分析报告[J]. 核科学与工程,2004,24(3):242-248.LU Donghua, BAI Xuesong, HUANG Yanping, 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(in Chinese). [12] 李忠朋. 管内流动轴向热流密度非均匀分布对临界热流密度的影响[J]. 核动力工程,1982,3(2):43-49.LI Zhongpeng. Influence of axially nonuniform heat flux distribution on critical heat flux for round tube flow[J]. Nuclear Power Engineering, 1982, 3(2): 43-49(in Chinese).
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