Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly
Journal Title: Strojnicky casopis - Journal of Mechanical Engineering - Year 2017, Vol 67, Issue 1
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.
Authors and Affiliations
Jakub Jakubec, Juraj Paulech, Vladimír Kutiš and Gabriel Gálik
Keywords
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- EP ID EP43905
- DOI https://doi.org/10.1515/scjme-2017-0007
- Views 207
- Downloads 0
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