Prediction of a subcooled boiling flow with advanced two-phase flow models

被引:121
作者
Yun, Byong-Jo [1 ]
Splawski, Andrew [2 ]
Lo, Simon [2 ]
Song, Chul-Hwa [3 ]
机构
[1] Pusan Natl Univ, Sch Mech Engn, Pusan 609735, South Korea
[2] CD Adapco, Didcot, Oxon, England
[3] Korea Atom Energy Res Inst, Taejon 305353, South Korea
基金
新加坡国家研究基金会;
关键词
BUBBLE DETACHMENT DIAMETERS; INTERFACIAL AREA TRANSPORT; UNIFIED MODEL; SYSTEMS; SIMULATION; ANNULUS; FORCE; PHASE;
D O I
10.1016/j.nucengdes.2011.08.067
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
Prediction of bubble size which governs interfacial transfer terms between the two phases is of importance for an accurate prediction of the subcooled boiling flow. In the present work, a mechanistic bubbles size model, S-gamma was examined to enhance the prediction capability of subcooled boiling flows for the CFD (computational fluid dynamics) code. In addition to this, advanced subcooled boiling models such as new wall boiling and two-phase logarithmic wall function models were also applied for an improvement of energy partitioning and two-phase turbulence models, respectively. The benchmark calculation against the DEBORA subcooled boiling data confirms that the S-gamma bubble size model with the two advanced subcooled boiling models shows good prediction results and is applicable to the wide range of flow conditions that are expected in the nominal and postulated accidental conditions of a nuclear power plant. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:351 / 359
页数:9
相关论文
共 42 条
[1]  
[Anonymous], 1970, HEAT TRANSFER 1970
[2]   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
[3]  
Bae B.U., 2010, T KOR NUCL SOC AUT M
[4]   Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off model [J].
Bae, Byoung-Uhn ;
Yun, Byong-Jo ;
Yoon, Han-Young ;
Song, Chul-Hwa ;
Park, Goon-Cherl .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (09) :2281-2294
[5]   Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations [J].
Bestion, D. ;
Anglart, H. ;
Caraghiaur, D. ;
Peturaud, P. ;
Smith, B. ;
Andreani, M. ;
Niceno, B. ;
Krepper, E. ;
Lucas, D. ;
Moretti, F. ;
Galassi, M. C. ;
Macek, J. ;
Vyskocil, L. ;
Koncar, B. ;
Hazi, G. .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2009, 2009
[6]   Shape and terminal velocity of single bubble motion: a novel approach [J].
Bozzano, G ;
Dente, M .
COMPUTERS & CHEMICAL ENGINEERING, 2001, 25 (4-6) :571-576
[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]  
Duncan W.J., 1972, MECH FLUIDS
[9]  
Garnier J., 2001, Multiph. Sci. Technol, V13, P1, DOI [10.1615/MultScienTechn.v13.i1-2.10, DOI 10.1615/MULTSCIENTECHN.V13.I1-2.10]
[10]   MULTIDIMENSIONAL MODELING OF TURBULENT 2-PHASE FLOWS IN STIRRED VESSELS [J].
GOSMAN, AD ;
LEKAKOU, C ;
POLITIS, S ;
ISSA, RI ;
LOONEY, MK .
AICHE JOURNAL, 1992, 38 (12) :1946-1956