CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Kutiš Vladimír; Jakubec Jakub; Paulech Juraj; Gálik Gálik; Sedlár Tibor

doi:10.1515/scjme-2016-0018

Journal of Mechanical Engineering (Nov 2016)

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Kutiš Vladimír,
Jakubec Jakub,
Paulech Juraj,
Gálik Gálik,
Sedlár Tibor

Affiliations

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

DOI: https://doi.org/10.1515/scjme-2016-0018
Journal volume & issue: Vol. 66, no. 2
pp. 55 – 62

Abstract

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The paper is focused on CFD analyses of the coolant flow in the nuclear reactor VVER 440. The goal of the analyses is to investigate the influence of the orifice diameter on the mass flow through individual fuel assemblies in the reactor core. The diameter of orifice can be changed during the operation of a nuclear power plant. Considered boundary conditions in the investigated region of the coolant are based on nominal coolant flow conditions in the nuclear reactor VVER 440.

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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