CFD analysis of flow field in a triangular rod bundle

被引：40
|
作者：
Toth, S. [1 ]
Aszodi, A. [1 ]
机构：
[1] Budapest Univ Technol & Econ, Inst Nucl Tech, H-1111 Budapest, Hungary
来源：
NUCLEAR ENGINEERING AND DESIGN | 2010年 / 240卷 / 02期
关键词：
TURBULENT-FLOW;
D O I：
10.1016/j.nucengdes.2008.08.020
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：
The flow field was investigated in subchannels of VVER-440 pressurized water cooled reactors' fuel assemblies (triangular lattice, P/D = 1.35). Impacts of the mesh resolution and turbulence model were studied in order to obtain guidelines for CFD calculations of VVER-440 rod bundles. Results were compared to measurement data published by Trupp and Azad in 1975. The study pointed out that RANS method with BSL Reynolds stress model using a sufficient fine grid can provide an accurate prediction for the turbulence quantities in this lattice. Applying the experiences of the sensitivity study thermal hydraulic processes were investigated in VVER-440 rod bundle sections. Based on the examinations the spacer grids have important effects on the cross flows, axial velocity and outlet temperature distribution of subchannels therefore they have to be modeled satisfactorily in CFD calculations. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码：352 / 363
页数：12
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