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

Jakubec Jakub; Paulech Juraj; Kutiš Vladimír; Gálik Gabriel

doi:10.1515/scjme-2017-0007

Journal of Mechanical Engineering (Apr 2017)

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

Jakubec Jakub,
Paulech Juraj,
Kutiš Vladimír,
Gálik Gabriel

Affiliations

Jakubec Jakub: Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Applied Mechanics and Mechatronics, Ilkovičová 3, 812 19Bratislava, Slovakia
Paulech Juraj: Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Applied Mechanics and Mechatronics, Ilkovičová 3, 812 19Bratislava, Slovakia
Kutiš Vladimír: Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Applied Mechanics and Mechatronics, Ilkovičová 3, 812 19Bratislava, Slovakia
Gálik Gabriel: Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Applied Mechanics and Mechatronics, Ilkovičová 3, 812 19Bratislava, Slovakia

DOI: https://doi.org/10.1515/scjme-2017-0007
Journal volume & issue: Vol. 67, no. 1
pp. 69 – 76

Abstract

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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.

Published in Journal of Mechanical Engineering

ISSN: 2450-5471 (Online)
Publisher: Sciendo
Country of publisher: Poland
LCC subjects: Technology: Engineering (General). Civil engineering (General)
Website: https://sciendo.com/journal/SCJME

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