Experimental study on critical heat flux in bilaterally heated narrow annuli

被引:33
作者
Wu, Y. W. [1 ]
Su, G. H. [1 ]
Qiu, S. Z. [1 ]
Hu, B. X. [1 ]
机构
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
关键词
Narrow annular channel; Critical heat flux; Bilateral heating; VERTICAL ANNULUS; LOW-PRESSURE; LOW-FLOW; 2-PHASE FLOW; WATER; GEOMETRY; TUBES;
D O I
10.1016/j.ijmultiphaseflow.2009.07.004
中图分类号
O3 [力学];
学科分类号
08 ; 0801 ;
摘要
Critical heat flux (CHF) experiments using deionized water as working fluid have been conducted in a range of pressure from 0.6 to 4.2 MPa, mass flow velocity from 60 to 130 kg/m(2) s and wall heat flux from 10 to 90 kW/m(2) for vertical narrow annuli with annular gap sizes of 0.95 and 1.5 mm. We found that the CHF, occurring only on the inside tube, or on the outside tube or on both tubes of the annular channel, depends on the heat flux ratio between surfaces of the outside and inside tubes. The CHF, occurring on the surface of the inside tube, reaches the maximum value under the pressure of 2.3 MPa while it occurring on the surface of the outside tube keeps increasing with the increase of the pressure. The CHF, occurring on the inside or outside tubes, increases with the increase of the mass flow velocity and the annular gap size: and decreases with the increase of critical quality and the other tube wall heat flux. Empirical correlations, which agree quite well with the experimental data, have been developed to predict the CHF occurring on surfaces of the inside or outside tubes of the narrow annular channel on the conditions of low pressure and low flow. (C) 2009 Elsevier Ltd. All rights reserved.
引用
收藏
页码:977 / 986
页数:10
相关论文
共 29 条
[1]  
BECKER KM, 1975, EUR 2 PHAS FLOW GROU
[2]   CRITICAL HEAT-FLUX OF NARROW VERTICAL ANNULI WITH CLOSED BOTTOMS [J].
CHANG, Y ;
YAO, SC .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 1983, 105 (01) :192-195
[3]   Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections [J].
Chun, SY ;
Moon, SK ;
Chung, HJ ;
Yang, SK ;
Chung, MK ;
Aritomi, M .
NUCLEAR ENGINEERING AND DESIGN, 2001, 205 (03) :265-279
[4]   Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions [J].
Chun, SY ;
Chung, HJ ;
Moon, SK ;
Yang, SK ;
Chung, MK ;
Schoesse, T ;
Aritomi, M .
NUCLEAR ENGINEERING AND DESIGN, 2001, 203 (2-3) :159-174
[5]  
CHUN SY, 1999, P 4 INT S XIAN CHIN, P380
[6]   A comparison of critical heat flux in tubes and bilaterally heated annuli [J].
Doerffer, S ;
Groeneveld, DC ;
Cheng, SC .
NUCLEAR ENGINEERING AND DESIGN, 1997, 177 (1-3) :105-120
[7]   ON THE PREDICTIONS OF CRITICAL HEAT-FLUX IN ROD BUNDLES AT LOW FLOW AND LOW-PRESSURE CONDITIONS [J].
ELGENK, MS ;
RAO, D .
HEAT TRANSFER ENGINEERING, 1991, 12 (04) :48-57
[8]   EXPERIMENTAL STUDIES OF CRITICAL HEAT-FLUX FOR LOW FLOW OF WATER IN VERTICAL ANNULI AT NEAR ATMOSPHERIC-PRESSURE [J].
ELGENK, MS ;
HAYNES, SJ ;
KIM, SH .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1988, 31 (11) :2291-2304
[9]   Influence of two-phase flow characteristics on critical heat flux in low pressure [J].
Inoue, A ;
Lee, SR .
EXPERIMENTAL THERMAL AND FLUID SCIENCE, 1999, 19 (03) :172-181
[10]  
JENSEN MK, 1976, AICHE S 16 NAT HEAT, V14, P205