Published October 2010 | Version v1
Journal article

Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology

  • 1. Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Section 2, Kuang-Fu Road, Hsingchu 30013, 325 Taiwan (China)

Description

With the dramatic progress in the computer processing power, computational fluid dynamics (CFD) methodology can be applied in investigating the detailed knowledge of thermal-hydraulic characteristics in the rod bundle, especially with the spacer grid. These localized information, including flow, turbulence, and heat transfer characteristics, etc., can assist in the design and the improvement of rod bundles for nuclear power plants. In this paper, a three-dimensional (3D) CFD model with the Reynolds stresses turbulence model is proposed to simulate these characteristics within the rod bundle and subsequently to investigate the effects of different types of grid on the turbulent mixing and heat transfer enhancement. Two types of grid designs are used herein, including the standard grid and split-vane pair one, respectively. Based on the CFD simulations, the secondary flow can be reasonably captured in the rod bundle with the grid. The split-vane pair grid would enhance both the flow mixing and the heat transfer capability more than the standard grid does, as clearly shown in the simulation results. In addition, compared with the results of experiment and correlation, the present predicted result for the Nusselt (Nu) number distribution downstream the grid shows reasonable agreement for the standard grid design. However, there is discrepancy in the decay trend of Nu number between the prediction and measurement for the split-vane pair gird. This would be improved by adopting the finer mesh (y+ < 1) simulation and Low-Reynolds form turbulence model, which is our future research work.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.05.021

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.05.021;
PII
S0029-5493(10)00346-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 3078-3086
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.