Flow Pattern Prediction in iPWR SMR with Natural Circulation by Coupling of RELAP and ANSYS CFX Code, M.Sc. Thesis Sharif University of Technology ; Ghafari, Mohsen (Supervisor)
Abstract
Selection of appropriate thermohydraulic tool for analyzing nuclear reactors is a trade of between accuracy and calculation run-time. Nuclear reactors analyses perform on two levels including system and sub-channel. In this regard or the system codes' one-dimensional approach is selected or the CFD codes for considering the three-dimensional and non-equilibrium phenomenon are employed. In this research a T-H tool for prediction of light-water cooled reactors core is developed. Although this code requires lower CPU and run-time in comparison with CFD codes, in contrast with system codes can report non-equilibrium and three-dimensional phenomenon. This code has a modular implementation based...
Cataloging briefFlow Pattern Prediction in iPWR SMR with Natural Circulation by Coupling of RELAP and ANSYS CFX Code, M.Sc. Thesis Sharif University of Technology ; Ghafari, Mohsen (Supervisor)
Abstract
Selection of appropriate thermohydraulic tool for analyzing nuclear reactors is a trade of between accuracy and calculation run-time. Nuclear reactors analyses perform on two levels including system and sub-channel. In this regard or the system codes' one-dimensional approach is selected or the CFD codes for considering the three-dimensional and non-equilibrium phenomenon are employed. In this research a T-H tool for prediction of light-water cooled reactors core is developed. Although this code requires lower CPU and run-time in comparison with CFD codes, in contrast with system codes can report non-equilibrium and three-dimensional phenomenon. This code has a modular implementation based...
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