Accesso libero

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Vladimír Kutiš

Vladimír Kutiš

Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Automotive Mechatronics, Department of Applied Mechanics and MechatronicsBratislava, Slovakia
Cerca questo autore su
Sciendo|Google Scholar
Kutiš, Vladimír
, 
Jakub Jakubec

Jakub Jakubec

Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Automotive Mechatronics, Department of Applied Mechanics and MechatronicsBratislava, Slovakia
Cerca questo autore su
Sciendo|Google Scholar
Jakubec, Jakub
, 
Juraj Paulech

Juraj Paulech

Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Automotive Mechatronics, Department of Applied Mechanics and MechatronicsBratislava, Slovakia
Cerca questo autore su
Sciendo|Google Scholar
Paulech, Juraj
, 
Gálik Gálik

Gálik Gálik

Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Automotive Mechatronics, Department of Applied Mechanics and MechatronicsBratislava, Slovakia
Cerca questo autore su
Sciendo|Google Scholar
Gálik, Gálik
 e 
Tibor Sedlár

Tibor Sedlár

Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Automotive Mechatronics, Department of Applied Mechanics and MechatronicsBratislava, Slovakia
Cerca questo autore su
Sciendo|Google Scholar
Sedlár, Tibor
  
17 dic 2016
CFD Analysis of Downcomer of Nuclear Reactor VVER 440's Cover Image
INFORMAZIONI SU QUESTO ARTICOLO
Articolo precedente
Articolo Successivo
Cita
Scarica la copertina
Pubblicato online: 17 dic 2016
Pagine: 55 - 62
DOI: https://doi.org/10.1515/scjme-2016-0018
Parole chiave
© 2016
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.

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.

Lingua:
Inglese
Frequenza di pubblicazione:
2 volte all'anno
Argomenti della rivista:
Ingegneria, Ingegneria meccanica, Basi dell'ingegneria meccanica, Meccanica
Feed RSS della rivista