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Flow Pattern Prediction in iPWR SMR with Natural Circulation by Coupling of RELAP and ANSYS CFX Code

Emampour, Mohammad Hassan | 2022

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 55496 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghafari, Mohsen
  7. Abstract:
  8. 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 on python language and no limitations is imposed on user for selection of core channels conditions. In the benchmark phase, its predictions in comparison with experimental and computational results had good conformity. Also the Small Modular Reactors (SMRs) and specially the integrated Pressurized Water Reactors (iPWRs) family have been selected as the final field of this research and employing the developed code.
  9. Keywords:
  10. Pressurized Water Reactor (PWR,WWER) ; Thermohydraulic Analysis ; Two Phase Flow ; Nuclear Reactors Accidents Analysis ; Thermohydraulic Code Development ; Integrated Pressurized Water Reactor (iPWR) ; Small Modular Reactor (SMR)

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