Application of a new drag coefficient model at CFD-simulations on free surface flows relevant for the nuclear reactor safety analysis

被引:15
作者
Deendarlianto [1 ,2 ]
Hoehne, Thomas [1 ]
Apanasevich, Pavel [1 ]
Lucas, Dirk [1 ]
Vallee, Christophe [1 ]
Beyer, Matthias [1 ]
机构
[1] Inst Safety Res, Helmholtz Zentrum Dresden Rossendorf eV, D-01314 Dresden, Germany
[2] Gadjah Mada Univ, Fac Engn, Dept Mech & Ind Engn, Yogyakarta 55281, Indonesia
关键词
Computational fluid dynamics (CFD); Algebraic interfacial area density (AIAD) model; Drag coefficient; Pressurized water reactor (PWR); Hot leg; Cold leg; 2-PHASE FLOW; FLUID; PTS;
D O I
10.1016/j.anucene.2011.09.010
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 paper presents different CFD-simulations on flows which are relevant for nuclear reactor safety using a new modeling approach for the interfacial drag at free surfaces. The developed drag coefficient model was implemented together with the Algebraic Interfacial Area Density (AIAD) model (Hohne, 2009) into the three-dimensional (3-D) computational fluid dynamics (CFD) code ANSYS-CFX. The applications considered include the prediction of counter-current flow limitations (CCFL) in a PWR hot leg, the development of hydraulic jump during the air-water co-current flow in a horizontal channel, and pressurized thermal shock (PTS) phenomena in a PWR cold leg and downcomer. For the modeling of these tasks, an Euler-Euler approach was used. This approach allows the use of different models depending on the local morphology. In the frame of an Euler-Euler simulation, the local morphology of the phases has to be considered in the drag model. To demonstrate the feasibility of the present approach, the computed main parameters of each case were compared with experimental data. It is shown that the CFD calculations agree well with the experimental data. This indicates that the AIAD model combined with new drag force modeling is a promising way to simulate the phenomena in frame of the Euler-Euler approach. Moreover the further validation of the model by including mass transfer effects should be carried out. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码:70 / 82
页数:13
相关论文
共 28 条
[1]   Modeling free surface flows relevant to a PTS scenario: Comparison between experimental data and three RANS based CFD-codes. Comments on the CFD-experiment integration and best practice guideline [J].
Bartosiewicz, Yann ;
Seynhaeve, J. -M. ;
Vallee, C. ;
Hoehne, T. ;
Lavieville, J. -M. .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (09) :2375-2381
[2]   Coupling of the interface tracking and the two-fluid models for the simulation of incompressible two-phase flow [J].
Cerne, G ;
Petelin, S ;
Tiselj, I .
JOURNAL OF COMPUTATIONAL PHYSICS, 2001, 171 (02) :776-804
[3]  
Coste P., 2010, P CFD4NRS 14 16 SEPT
[4]  
Coste P., 2008, P 16 INT C NUCL ENG
[5]   Experimental study on the air/water counter-current flow limitation in a model of the hot leg of a pressurized water reactor [J].
Deendarlianto ;
Vallee, Christophe ;
Lucas, Dirk ;
Beyer, Matthias ;
Pietruske, Heiko ;
Carl, Helmar .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (12) :3389-3402
[6]  
Egorov Y, 2004, 5 EUR FRAM PROGR ECO
[7]   NUMERICAL CALCULATION OF TIME-DEPENDENT VISCOUS INCOMPRESSIBLE FLOW OF FLUID WITH FREE SURFACE [J].
HARLOW, FH ;
WELCH, JE .
PHYSICS OF FLUIDS, 1965, 8 (12) :2182-&
[8]   VOLUME OF FLUID (VOF) METHOD FOR THE DYNAMICS OF FREE BOUNDARIES [J].
HIRT, CW ;
NICHOLS, BD .
JOURNAL OF COMPUTATIONAL PHYSICS, 1981, 39 (01) :201-225
[9]  
Hohne T., 2010, J COMPUTATIONAL MULT, V2, P131, DOI [DOI 10.1260/1757-482X.2.3.131, 10.1260/1757-482X.2.3.131]
[10]  
IAEA, 2001, IAEAEBPWWER08