Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly
, , y | 03 may 2017
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Publicado en línea: 03 may 2017
Páginas: 69 - 76
DOI: https://doi.org/10.1515/scjme-2017-0007
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© 2017
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.
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.