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In nuclear reactor system research, the multiscale coupled thermal-hydraulic (T-H) code and CFD is one of most prevalent research areas, it could help improve simulation fidelity optimize design. Additionally, a new idea known as function fitting method (FFM) for coupling parameter distribution has been newly proposed exchanging data on interface, which uses math equations to present velocity c...

Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and moving electro-conductive fluid, are crucial for design of magnetic-confinement fusion reactors and, specifically, breeding blanket concepts that adopt liquid metals (LMs) as working fluids. Computational tools employed lead fusion-relevant physical analysis, but dedicated MHD code able simulate all phenome...

It is known, that the phenomena of phase change and boiling crisis are not yet fully deciphered, which leads to generation technical problems, such as frequent breakdowns accidental shutdowns in thermal installations. The main objective this study numerical analysis an ascending flow during a vertical channel by Relap5/Mod3.2 code. This code can helps heat transfer convection, boiling, condensa...

The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design WCLL-BB (water-cooled lead-lithium breeding blanket). Research activities are ongoing master phenomena and processes that occur during postulated accident, enhance predictive capability reliability numerical tools, validate computer models, codes, procedures for their applications. Followi...

The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using the neutronics analysis code SCALE6.0 and thermal-hydraulics kinetics modeling RELAP5-3D with objective to devise, analyze, evaluate feasibility stability of a start-up procedure for this reactor natural circulation coolant under Loss Of Offsite Power (LOOP) conditions. This Generation IV design has been initially ...