CFD Analysis of Thermo-hydraulic Behaviour in the VVER-1000 Reactor Using COMSOL Multiphysics

This article presents a two-dimensional Computational Fluid Dynamic (CFD) of the thermohydraulic behaviour of VVER -1000 reactor vessel based on COMSOL Multiphysics. The model works in a steady- state condition to examine the distribution of the flow of the coolant, along with temperature gradient and pressure differences in the reactor territory. Background conditions are specified as 515m2s/inlet flow rate and inflow temperature set at 563.15 K and natural convection imposed on the exterior of the reactor wall in order to model natural convection with the environment. The two stationary simulations provide finer results in terms of temperature, velocity and pressure contours which helps one evaluate flow uniformity and heat transfer properties. Scientific outputs are read and calculated across three sampling cut lines and found to show the effect that coolant interactions have on both local thermal conditions and pressure stability. The result of this work will help identify the VVER-1000 reactor cooling performance better and make a mathematical basis of future three- dimensional and transient analysis.

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Publication Details

Journal
Springer Link (Chiba Institute of Technology)
Published
2026-03-03
DOI
https://doi.org/10.1051/epjconf/202635504012/pdf
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
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article

CFD Analysis of Thermo-hydraulic Behaviour in the VVER-1000 Reactor Using COMSOL Multiphysics

K. Yu. Rashidov, Utkir Mustafoyev, Amirbek Ikramov, Guzal Bobomurodova et al.
Springer Link (Chiba Institute of Technology)
Nuclear Engineering Thermal-Hydraulics
article

CFD Analysis of Thermo-hydraulic Behaviour in the VVER-1000 Reactor Using COMSOL Multiphysics

K. Yu. Rashidov, Utkir Mustafoyev, Amirbek Ikramov, Guzal Bobomurodova, Renata Monasipova, Moxinur Razzokova, Diydor Abdukhamidov
article en

Abstract

This article presents a two-dimensional Computational Fluid Dynamic (CFD) of the thermohydraulic behaviour of VVER -1000 reactor vessel based on COMSOL Multiphysics. The model works in a steady- state condition to examine the distribution of the flow of the coolant, along with temperature gradient and pressure differences in the reactor territory. Background conditions are specified as 515m2s/inlet flow rate and inflow temperature set at 563.15 K and natural convection imposed on the exterior of the reactor wall in order to model natural convection with the environment. The two stationary simulations provide finer results in terms of temperature, velocity and pressure contours which helps one evaluate flow uniformity and heat transfer properties. Scientific outputs are read and calculated across three sampling cut lines and found to show the effect that coolant interactions have on both local thermal conditions and pressure stability. The result of this work will help identify the VVER-1000 reactor cooling performance better and make a mathematical basis of future three- dimensional and transient analysis.

Springer Link (Chiba Institute of Technology)
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Nuclear Engineering Thermal-Hydraulics
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