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Thermal Hydraulic Analysis of Prismatic Htgr with Natural Convection Using Porous Media Approach (in Case of Lose of Forced Circulation Accident)

Golshanee, Masoud | 2013

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 44157 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghofrani, Mohammad Bagher
  7. Abstract:
  8. In this study, the thermal-hydraulic analysis of prismatic HTGR’s core with natural convection has been studied using porous media approach. VHTR are the new generation reactors which due to special neutron and thermo physical properties have highly inherent safety. In lose of forced circulation accident, decay heat is transferred from core to pressure vessel wall and then to water tubes in concrete wall at reactor cavity with conduction, convection and radiation automatically. In this case the high volume of decay heat is stored in graphite block with high thermal capacity and is prevented the instantaneous temperature rising.
    The aim of this study is justifying inherent safety of HTGR in accident condition using porous media approach. In this study, helium natural convection through pressure vessel and heat transfer from core to outside of pressure vessel has been modeled at lose of forced circulation accident. Heat transfer’s model is composed of convection, conduction and radiation through pressure vessel. Reactor core containing fluid flow channels is simulated to porous media and governing equations for fluid flow and heat transfer has been solved through geometry using CFD. The results are in good agreement with previous analysis in this area and maximum temperature in the core does not exceed from HTGR’s safety criteria and reactor is safe in all conditions
  9. Keywords:
  10. Inherent Safety ; High Themprature Gas-Cooled Reactor (HTGR) ; Porous Media Approach ; Helyom Natural Circulation ; Thermohydraulic Analysis ; Loss of Forced Circulation

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