Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions

被引:41
|
作者
Chun, SY
Chung, HJ
Moon, SK
Yang, SK
Chung, MK
Schoesse, T
Aritomi, M
机构
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
[2] Tokyo Inst Technol, Nucl Reactors Res Lab, Meguro Ku, Tokyo 152, Japan
关键词
D O I
10.1016/S0029-5493(00)00307-1
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Critical heat flux (CHF) experiments have been carried out in a wide range of pressure for an internally heated vertical annulus. The experimental conditions covered a range of pressure from 0.57 to 15.01 MPa, mass fluxes of 0 kg m(-2) s(-1) and from 200 to 650 kg m(-2) s(-1), and inlet subcoolings from 85 to 413 kJ kg(-1). Most of the CHFs were identified to the dryout of the liquid him in the annular-mist flow. For the mass fluxes of 550 and 650 kg m(-2) s(-1), the CHFs had a maximum value at a pressure of 2-3 MPa, and the pressure at the maximum CHF values had a trend moving toward the pressure at the peak value of pool boiling CHF as the mass flux decreased. The CHF data under a zero mass flux condition indicate that both the effects of pressure and inlet subcooling on the CHF were smaller, compared with those for the CHF with a net water upflow. The Doerffer correlation using the 1995 CHF look-up table and the Bowring correlation show a good prediction capability for the present CHF data. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:159 / 174
页数:16
相关论文
共 50 条
  • [21] Critical Heat Flux in Non-uniformly Heated Tube Under Low-Pressure and Low-Mass-Flux Condition
    Umekawa, Hisashi
    Kitajima, Tetsuo
    Hirayama, Mio
    Ozawa, Mamoru
    Mishima, Kaichiro
    Saito, Yasushi
    HEAT TRANSFER-ASIAN RESEARCH, 2006, 35 (01): : 47 - 60
  • [22] EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS
    Vlcek, Daniel
    Suk, Ladislav
    Stevanka, Kamil
    Petrosyan, Taron
    STUDENT CONFERENCE ON NUCLEAR ENGINEERING (SIMANE 2020), 2020, 28 : 50 - 58
  • [23] DRYOUT INCIPIENCE AND CRITICAL HEAT FLUX IN SATURATED FLOW BOILING OF REFRIGERANTS IN A VERTICAL UNIFORMLY HEATED MICROCHANNEL
    Martin-Callizo, Claudi
    Ali, Rashid
    Palm, Bjorn
    PROCEEDINGS OF THE 6TH INTERNATIONAL CONFERENCE ON NANOCHANNELS, MICROCHANNELS, AND MINICHANNELS, PTS A AND B, 2008, : 705 - 712
  • [24] Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions
    Park, C
    Chang, SH
    Baek, WP
    NUCLEAR ENGINEERING AND DESIGN, 1998, 183 (03) : 235 - 247
  • [25] Heat transfer for flow boiling of water and critical heat flux in a half-heated round tube under low-pressure conditions
    Kobayashi, Toshiyuki
    Mishima, Kaichiro
    Heat Transfer - Asian Research, 2002, 31 (03): : 149 - 164
  • [26] A DATA SET OF CRITICAL HEAT-FLUX OF BOILING R-12 IN UNIFORMLY HEATED VERTICAL TUBES UNDER TRANSIENT CONDITIONS
    CELATA, GP
    CUMO, M
    DANNIBALE, F
    EXPERIMENTAL THERMAL AND FLUID SCIENCE, 1992, 5 (01) : 78 - 107
  • [27] Critical heat flux under flow oscillation of water at low-pressure, low-flow conditions
    Kim, Yun Il
    Baek, Won-Pil
    Chang, Soon Heung
    Nuclear Engineering and Design, 1999, 193 (01): : 131 - 143
  • [28] Critical heat flux under flow oscillation of a water at low-pressure, low-flow conditions
    Kim, YI
    Baek, WP
    Chang, SH
    NUCLEAR ENGINEERING AND DESIGN, 1999, 193 (1-2) : 131 - 143
  • [29] Prediction of critical heat flux (CHF) for the high-pressure region in uniformly heated vertical round tubes
    Song, Meiqi
    Liu, Xiaojing
    Cheng, Xu
    ANNALS OF NUCLEAR ENERGY, 2021, 158 (158)
  • [30] CRITICAL HEAT-FLUX OF COUNTER-FLOW BOILING IN A UNIFORMLY HEATED VERTICAL TUBE WITH A CLOSED BOTTOM
    KATTO, Y
    HIRAO, T
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1991, 34 (4-5) : 993 - 1001