Critical heat flux and turbulent mixing in hexagonal tight rod bundles

被引:32
|
作者
Cheng, X [1 ]
Müller, U [1 ]
机构
[1] Res Ctr Karlsruhe, Inst Appl Thermo & Fluiddynam, D-76021 Karlsruhe, Germany
关键词
critical heat flux; turbulent mixing; tight rod bundle;
D O I
10.1016/S0301-9322(98)00027-5
中图分类号
O3 [力学];
学科分类号
08 ; 0801 ;
摘要
Experimental and theoretical investigations have been performed on critical heat flux (CHF) and turbulent mixing in tight, hexagonal, 7-rod bundles. Freon-12 was used as working fluid due to its low latent heat, low critical pressure and well known properties. It has been found that the two-phase mixing coefficient depends mainly on mass flux. It increases with decreasing mass flux and ranges from 0.01 to 0.04 for the test conditions considered. More than 900 CHF data points have been obtained in a large range of parameters: pressure 1.0-3.0 MPa and mass flux 1.0-6.0 Mg/m(2)s. The effect of different parameters on CHF has been analysed. It has been found that the effect of pressure, mass flux and vapour quality on CHF is similar to that observed in circular tubes. Nevertheless, the CHF in the tight rod bundle is much lower than that in a circular tube of the same equivalent hydraulic diameters. The effect of wire wraps on CHF is mainly dependent on local vapour qualities and subsequently on flow regimes. Based on subchannel flow conditions, the effect of radial power distribution on CHF is small. Comparison of the test results with CHF prediction methods underlines the need for further work. (C) 1998 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:1245 / 1263
页数:19
相关论文
共 50 条
  • [21] A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles
    Jeong, Hae-Yong
    Ha, Kwi-Seok
    Kwon, Young-Min
    Lee, Yong-Bum
    Hahn, Dohee
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2007, 50 (5-6) : 908 - 918
  • [22] A study on geometric shape factors for turbulent mixing coefficents in rod bundles
    Shen, Danhong
    Liu, Xiaojing
    Cheng, Xu
    NUCLEAR ENGINEERING AND DESIGN, 2019, 353
  • [23] Two-phase turbulent mixing and buoyancy drift in rod bundles
    Carlucci, LN
    Hammouda, N
    Rowe, DS
    NUCLEAR ENGINEERING AND DESIGN, 2004, 227 (01) : 65 - 84
  • [24] An improved critical power correlation for tight-lattice rod bundles
    Liu, Wei
    Kureta, Masatoshi
    Yoshida, Hiroyuki
    Ohnuki, Akira
    Akimoto, Hajime
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2007, 44 (04) : 558 - 571
  • [25] An improved critical power correlation for tight-lattice rod bundles
    Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan
    J Nucl Sci Technol, 4 (559-571):
  • [26] APPLICATION OF TABLES OF CRITICAL HEAT FLUXES TO ROD BUNDLES
    SUCHY, P
    ULRYCH, G
    KEMNER, H
    KURZ, E
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 15 - 17
  • [27] ON THE PREDICTIONS OF CRITICAL HEAT-FLUX IN ROD BUNDLES AT LOW FLOW AND LOW-PRESSURE CONDITIONS
    ELGENK, MS
    RAO, D
    HEAT TRANSFER ENGINEERING, 1991, 12 (04) : 48 - 57
  • [28] Development of a new criterion for predicting critical heat flux in rod bundles with supercritical water flowing upward
    Han, Huirui
    Zhang, Chao
    Jiang, Jing
    JOURNAL OF SUPERCRITICAL FLUIDS, 2024, 209
  • [29] Mechanistic model of critical heat flux in rod bundles based on a high-precision subchannel code
    Guo, Junliang
    Shan, Jianqiang
    Jiang, Li
    Peng, Yujiao
    Gui, Miao
    NUCLEAR ENGINEERING AND DESIGN, 2024, 422
  • [30] EFFECTS ON CRITICAL HEAT-FLUX OF LOCAL HEAT-FLUX SPIKES OR LOCAL FLOW BLOCKAGE IN PRESSURIZED WATER REACTOR ROD BUNDLES
    HILL, KW
    MOTLEY, FE
    CADEK, FF
    CASTERLINE, JE
    MECHANICAL ENGINEERING, 1975, 97 (04) : 67 - 67