CFD methodology and validation for single-phase flow in PWR fuel assemblies

被引:108
作者
Conner, Michael E. [1 ]
Baglietto, Emilio [2 ]
Elmahdi, Abdelaziz M. [1 ]
机构
[1] Westinghouse Nucl Fuel, Columbia, SC 29250 USA
[2] New York Off, CD Adapco, Melville, NY 11747 USA
关键词
HEAT-TRANSFER; ROD BUNDLES;
D O I
10.1016/j.nucengdes.2009.11.031
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 the CFD modeling methodology and validation for steady-state, normal operation in a PWR fuel assembly. This work is part of a program that is developing a CFD methodology for modeling and predicting single-phase and two-phase flow conditions downstream of structural grids that have mixing devices. The purpose of the mixing devices (mixing vanes in this case) is to increase turbulence and improve heat transfer characteristics of the fuel assembly. The detailed CFD modeling methodology for single-phase flow conditions in PWR fuel assemblies was developed using the STAR-CD CFD code. This methodology includes the details of the computational mesh, the turbulence model used, and the boundary conditions applied to the model. The methodology was developed by benchmarking CFD results versus small-scale experiments. The experiments use PIV to measure the lateral flow field downstream of the grid, and thermal testing to determine the heat transfer characteristics of the rods downstream of the grid. The CFD results and experimental data presented in the paper provide validation of the single-phase flow modeling methodology. Two-phase flow CFD models are being developed to investigate two-phase conditions in PWR fuel assemblies, and these can be presented at a future CFD Workshop. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:2088 / 2095
页数:8
相关论文
共 12 条
[1]  
CD-adapco Group, 2005, STAR CD MAN VERS 3 2
[2]  
Conner M., 2007, P 2007 INT LWR FUEL
[3]  
Conner M.E., 2005, P 2005 WAT REACT FUE
[4]   Single-phase convective heat transfer in rod bundles [J].
Holloway, Mary V. ;
Beasley, Donald E. ;
Conner, Michael E. .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (04) :848-858
[5]   The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles [J].
Holloway, MV ;
Conover, TA ;
McClusky, HL ;
Beasley, DE ;
Conner, ME .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2005, 127 (06) :598-605
[6]   The effect of support grid features on local, single-phase heat transfer measurements in rod bundles [J].
Holloway, MV ;
McClusky, HL ;
Beasley, DE ;
Conner, ME .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2004, 126 (01) :43-53
[7]  
Liu B., 2004, P 2004 INT M LWR FUE
[8]   Mapping surface properties of sinusoidal roughness standards by TPM [J].
Liu, X. ;
Rubert, P. .
7th International Symposium on Measurement Technology and Intelligent Instruments, 2005, 13 :20-23
[9]  
McClusky H.L., 2003, P 11 INT C NUCL ENG
[10]   Development of swirling flow in a rod bundle subchannel [J].
McClusky, HL ;
Holloway, MV ;
Beasley, DE ;
Conner, ME .
JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME, 2002, 124 (03) :747-755