Post-CHF heat transfer during two-phase upflow boiling of R-407C in a vertical pip

被引:6
作者
Sindhuja, R. [1 ]
Balakrishnan, A. R. [1 ]
Murthy, S. Srinivasa [2 ]
机构
[1] Indian Inst Technol, Dept Chem Engn, Madras 600036, Tamil Nadu, India
[2] Indian Inst Technol, Dept Mech Engn, Madras 600036, Tamil Nadu, India
关键词
Boiling heat transfer; Post critical heat flux; Vertical pipe; R-407C; FLOW VISUALIZATION; TRANSFER REGION; HIGH-PRESSURES; DRYOUT REGIME; PREDICTION; FLUX; TUBE; NONEQUILIBRIUM; MODEL;
D O I
10.1016/j.applthermaleng.2009.07.016
中图分类号
O414.1 [热力学];
学科分类号
摘要
This paper reports a study of heat transfer in the post-critical heat flux (post-CHF) regime under forced convective upflow conditions in a uniformly heated vertical tube of 12.7 mm internal diameter and 3 length. Experiments were conducted with non-azeotropic ternary refrigerant mixture R-407C for reduced pressures ranging from 0.37 to 0.75, mass flux values from 1200 to 2000 kg/m(2) s and heat nux from 50 to 80 kw/m(2). Data shows a considerable effect of system pressure on the post-CHF heat transfer coefficient for specified mass and heat fluxes. The post-CHF heat transfer coefficients for R-407C are compared with three existing correlations which are found to over predict the current data. A modified correlation represent the experimental data for R-407C is presented. (C) 2009 Elsevier Ltd. All rights reserved.
引用
收藏
页码:167 / 173
页数:7
相关论文
共 25 条
[1]  
Becker K.M., 1983, EXPT INVESTIGATION P
[2]  
BECKER KM, 1992, KTHNEL54 DEP NUCL RE
[3]   CRITICAL HEAT-FLUX IN UPFLOW CONVECTIVE BOILING OF REFRIGERANT BINARY-MIXTURES [J].
CELATA, GP ;
CUMO, M ;
SETARO, T .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1994, 37 (07) :1143-1153
[4]   A look-up table for fully developed film-boiling heat transfer [J].
Groeneveld, DC ;
Leung, LKH ;
Vasic', AZ ;
Guo, YJ ;
Cheng, SC .
NUCLEAR ENGINEERING AND DESIGN, 2003, 225 (01) :83-97
[5]   POST-DRYOUT HEAT-TRANSFER - PHYSICAL MECHANISMS AND A SURVEY OF PREDICTION METHODS [J].
GROENEVELD, DC .
NUCLEAR ENGINEERING AND DESIGN, 1975, 32 (03) :283-294
[6]   PREDICTION OF THERMAL NONEQUILIBRIUM IN POST-DRYOUT REGIME [J].
GROENEVELD, DC ;
DELORME, GGJ .
NUCLEAR ENGINEERING AND DESIGN, 1976, 36 (01) :17-26
[7]  
GROENEVELD DC, 1995, NUCL ENG DES, V163, P1
[8]  
GROENEVELD DC, 1973, NATL TOP M WAT REAC
[9]   Calculation of dryout and post-dryout heat transfer for tube geometry [J].
Hoyer, N .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1998, 24 (02) :319-334
[10]   FLOW VISUALIZATION STUDY OF INVERTED ANNULAR-FLOW OF POST DRYOUT HEAT-TRANSFER REGION [J].
ISHII, M ;
DEJARLAIS, G .
NUCLEAR ENGINEERING AND DESIGN, 1987, 99 :187-199