Development of a critical heat flux correlation based on an annular film dryout mechanistic model under the annular flow conditions

被引:0
|
作者
Yodo, Tadakatsu [1 ]
Odaira, Naoya [2 ]
Ito, Daisuke [2 ]
Ito, Kei [2 ]
Saito, Yasushi [2 ]
机构
[1] Kyoto Univ, Grad Sch Energy Sci, Yoshida Hommachi,Sakyo Ku, Kyoto 6068501, Japan
[2] Kyoto Univ, Inst Integrated Radiat & Nucl Sci, Osaka, Japan
关键词
Critical heat flux; mechanistic model-based correlation; CHF correlation; dryout mechanistic model; thermal hydraulic; safety analysis; PREDICTION; CHF; FRACTION; REGIME;
D O I
10.1080/00223131.2023.2177761
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
This study proposes a mechanistic model-based correlation for the critical heat flux to meet the practical requirements for the design and safety analysis of light water reactors. The correlation is based on an annular film dryout mechanistic model for a single tube, which needs numerical integration from the onset of annular flow to the dryout point, expressed as an explicit non-dimensional equation to ensure a wide applicable range of coolant conditions. The correlation predicts a critical heat flux for the annular flow region in the pressure range of 1-16 MPa, the mass velocity range of 500-3000 kg/m(2)s, and the thermal equilibrium quality range of 0.05-0.7. The prediction by the developed correlation agrees well with that of the existing mechanistic model without any numerical integration of the annular flow conditions.
引用
下载
收藏
页码:1182 / 1193
页数:12
相关论文
共 50 条
  • [21] Critical heat flux of water in vertical annular channel with a short heated rod under low pressure and low flow conditions
    Chen, Sen
    Chen, Lixin
    Tian, Xiaoyan
    Kang, Xiaoya
    Luo, Xiaofei
    Li, Da
    Li, Weitong
    Li, Huaqi
    EXPERIMENTAL THERMAL AND FLUID SCIENCE, 2023, 145
  • [22] Dryout-type critical heat flux in vertical upward annular flow: effects of entrainment rate, initial entrained fraction and diameter
    Wu, Zan
    Wadekar, Vishwas
    Wang, Chenglong
    Sunden, Bengt
    HEAT AND MASS TRANSFER, 2018, 54 (01) : 81 - 90
  • [23] EFFECT OF AXIAL HEAT FLUX DISTRIBUTION ON CRITICAL HEAT FLUX IN ANNULAR 2-PHASE FLOW
    TODREAS, NE
    ROHSENOW, WM
    CHEMICAL ENGINEERING PROGRESS, 1966, 62 (07) : 88 - &
  • [24] A MECHANISTIC CRITICAL HEAT-FLUX MODEL FOR SUBCOOLED FLOW BOILING BASED ON LOCAL BULK FLOW CONDITIONS
    LEE, CH
    MUDAWAR, I
    INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1988, 14 (06) : 711 - 728
  • [25] Numerical and analytical description of the critical heat flux in annular channels with water flow
    Bobkov, V.P.
    Sudnitsyn, O.A.
    Sudnitsyna, M.O.
    Atomnaya Energiya, 1998, 84 (02): : 114 - 123
  • [26] Numerical and analytical description of the critical heat flux for water flow in annular channels
    Bobkov, VP
    Sudnitsyn, OA
    Sudnitsyna, MO
    ATOMIC ENERGY, 1998, 84 (02) : 98 - 105
  • [27] Investigation of critical heat flux of annular flow in vertical upward round tube
    Fan, Pu
    Qiu, Sui-Zheng
    Jia, Dou-Nan
    Hedongli Gongcheng/Nuclear Power Engineering, 2006, 27 (05): : 42 - 47
  • [28] Numerical and analytical description of the critical heat flux for water flow in annular channels
    V. P. Bobkov
    O. A. Sudnitsyn
    M. O. Sudnitsyna
    Atomic Energy, 1998, 84 : 98 - 105
  • [29] EFFECT OF LOCAL FLUX PEAKS ON CRITICAL HEAT FLUX IN ANNULAR 2-PHASE FLOW
    TODREAS, NE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (02): : 563 - +
  • [30] Review on Development of Critical Heat Flux Mechanistic Model
    Liu W.
    Peng S.
    Jiang G.
    Liu Y.
    Deng J.
    Hu Y.
    Liu X.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 (03): : 211 - 217