A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
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 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
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
Kutiš Vladimír (author) / Jakubec Jakub (author) / Paulech Juraj (author) / Gálik Gálik (author) / Sedlár Tibor (author)
2016
Article (Journal)
Electronic Resource
Unknown
Metadata by DOAJ is licensed under CC BY-SA 1.0
Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
| DOAJ | 2017