<abstract xmlns="http://www.w3.org/1999/xhtml"><p> 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.</p></abstract>

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.

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

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,

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,

Strojnícky časopis - Journal of Mechanical Engineering

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

{"article-title":"CFD Analysis of Downcomer of Nuclear Reactor VVER 440"}

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...

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Publicado en línea: 17 dic 2016

Páginas: 55 - 62

DOI: https://doi.org/10.1515/scjme-2016-0018

Palabras clave
CFD simulation, ANSYS CFX, thermal-hydraulics, nuclear reactor, VVER 440

© 2016

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Publicado en línea: 17 dic 2016

Páginas: 55 - 62

DOI: https://doi.org/10.1515/scjme-2016-0018

Palabras claveCFD simulation, ANSYS CFX, thermal-hydraulics, nuclear reactor, VVER 440

© 2016

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Palabras clave
CFD simulation, ANSYS CFX, thermal-hydraulics, nuclear reactor, VVER 440