Investigation of subcooled flow boiling model under low pressure

被引:0
作者
Pu, Fan [1 ]
机构
[1] Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China
来源
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B | 2011年
关键词
Subcooled flow boiling; Two fluid model; Multiphase flow; DIAMETER; WATER;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Two fluid model integrating a set of closure relationships (such as inter-phase heat transfer model, inter-phase mass transfer model, inter-phase momentum transfer model, mean bubble diameter model, bubble departure diameter model, bubble departure frequency model, onset of nucleate boiling model, wall heat flux partition model) are applied to solve the local flow and heat transfer of subcooled flow boiling under low pressure, and local flow parameters such as volume fraction, liquid velocity, vapor phase etc. are obtained using developed code. The subcooled flow boiling results predicted in this paper are compared to the subcooled flow boiling experimental results of TH Lee([1]) etc.in annular channel with inner tube heated uniformly and adiabatic outer tube, and they agree well. The code can also be used to predict the multiphase flow field in power reactor core when the subcooled flow boiling take place and the critical heat flux of Departure Nucleate Boiling(DNB) in reactor core and it is meaningful for reactor core design.
引用
收藏
页码:193 / 204
页数:12
相关论文
共 26 条
[1]  
*AEA TECHN PLC, 1999, CFX 4 3 SOLV MAN, P64912
[2]   CFD application to prediction of void distribution in two-phase bubbly flows in rod bundles [J].
Anglart, H ;
Nylund, O .
NUCLEAR ENGINEERING AND DESIGN, 1996, 163 (1-2) :81-98
[3]  
[Anonymous], 3 INT C MULT FLOW IC
[4]  
[Anonymous], 1989, NUREGCR5273
[5]   ANALYSIS OF PHASE DISTRIBUTION IN FULLY-DEVELOPED LAMINAR BUBBLY 2-PHASE FLOW [J].
ANTAL, SP ;
LAHEY, RT ;
FLAHERTY, JE .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1991, 17 (05) :635-652
[6]   Onset of nucleate boiling and active nucleation site density during subcooled flow boiling [J].
Basu, N ;
Warrier, GR ;
Dhir, VK .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2002, 124 (04) :717-728
[7]   A PHOTOGRAPHIC STUDY OF POOL BOILING IN THE REGION OF THE CRITICAL HEAT FLUX [J].
COLE, R .
AICHE JOURNAL, 1960, 6 (04) :533-538
[8]  
Delhaye JIM, 1981, 2 PHASE FLOW HEAT TR
[9]   THE VIRTUAL MASS AND LIFT FORCE ON A SPHERE IN ROTATING AND STRAINING INVISCID FLOW [J].
DREW, DA ;
LAHEY, RT .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1987, 13 (01) :113-121
[10]  
Fritz W, 1936, PHYS Z, V37, P391