CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Journal of Mechanical Engineering

Paulech Juraj¹  Sedlár Tibor¹  Jakubec Jakub¹  Gálik Gálik¹  Kutiš Vladimír² 

[1] 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 19 Bratislava, Slovakia;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 19 Bratislava, Slovakia;

关键词: cfd simulation;    ansys cfx;    thermal-hydraulics;    nuclear reactor;    vver 440;   

DOI  :  10.1515/scjme-2016-0018

来源: DOAJ

【 摘 要 】

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.

【 授权许可】

Unknown