Investigating flow and heat transfer characteristics in a fuel bundle with split-vane pair grids by CFD methodology-Reference-Cited by-同舟云学术

Investigating flow and heat transfer characteristics in a fuel bundle with split-vane pair grids by CFD methodology

Published:2014-02 Issue: Volume:64 Page:93-99
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Tseng Y.S.,Ferng Y.M.,Lin C.H.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. ANSYS Inc., 2012. ANSYS Fluent 14.

2. Numerical simulation of turbulent flow in a 37-rod bundle;Chang;Nucl. Eng. Des.,2007

3. CFD methodology and validation for single-phase flow in PWR fuel assemblies;Conner;Nucl. Eng. Des.,2010

4. Conner, M.E., Smith III, L.D., Holloway, M.V., Beasley, D.E., 2005. Heat transfer coefficient testing in nuclear fuel rod bundles with mixing vane grids. In: Proceedings of the 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, October 2-6.

5. The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles;Holloway;J. Heat Transf.,2005

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