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Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly Cover

Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly

Open Access
|May 2017

Abstract

The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was investigated. Only steady-state analyses were performed. Boundary conditions are based on operating conditions. ANSYS CFX is chosen as the main CFD software tool, where all analyses are performed.

DOI: https://doi.org/10.1515/scjme-2017-0007 | Journal eISSN: 2450-5471 | Journal ISSN: 0039-2472
Language: English
Page range: 69 - 76
Published on: May 3, 2017
Published by: Slovak University of Technology in Bratislava
In partnership with: Paradigm Publishing Services
Publication frequency: 2 issues per year

© 2017 Jakub Jakubec, Juraj Paulech, Vladimír Kutiš, Gabriel Gálik, published by Slovak University of Technology in Bratislava
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.