Development of methods for thermo-hydraulic simulation of nuclear reactors and similar systems in normal working conditions and in transient processes
Dmitry Zviaga

TL;DR
This paper develops a numerical CFD methodology for simulating natural convection compressible flows with high temperature differences and complex geometries, relevant for nuclear reactor core analysis.
Contribution
It introduces a comprehensive CFD-based approach combining pressure algorithms and immersed boundary methods for complex, high-temperature convection flows.
Findings
Verification against literature data confirms accuracy.
Method successfully models high temperature difference flows.
Results demonstrate applicability to nuclear reactor simulations.
Abstract
The goal of this report is to present the final project conducted in order to fulfill the requirements of the M.Sc. degree at the Department of Mechanical Engineering, Ben-Gurion University (BGU) of the Negev. The project comprises theoretical research investigating natural convection compressible flow with high temperature differences and with complex geometries. The research motivation comes from long-term research investigating and simulating the steady state and transient multiphase flow regimes existing in the reactor core, that was established by the Soreq Nuclear Center. The main objective of this project is to develop a comprehensive numerical methodology that is capable of theoretical modeling of natural convection compressible flow with high temperature differences and with complex geometries, using standard techniques of computational fluid dynamics (CFD) - pressure-based…
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Taxonomy
TopicsLattice Boltzmann Simulation Studies · Fluid Dynamics Simulations and Interactions · Granular flow and fluidized beds
