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Numerical Analysis of Heat Transfer Phenomena When Mitigating Severe Accident With External Reactor Vessel Flooding

[+] Author Affiliations
Tae Hyub Hong, Hyeong Taek Kim, Chan Kook Moon

Central Research Institute of KHNP, Daejeon, Republic of Korea

Paper No. ICONE20-POWER2012-54444, pp. 457-462; 6 pages
  • 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
  • Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes
  • Anaheim, California, USA, July 30–August 3, 2012
  • Conference Sponsors: Nuclear Engineering Division, Power Division
  • ISBN: 978-0-7918-4498-4
  • Copyright © 2012 by ASME


The concept of in-vessel retention (IVR) is the stabilization of the reactor pressure vessel (RPV) by cooling the outside vessel wall with water in a severe accident. This study offers detailed information on complex thermal hydrodynamic phenomena, including boiling and two-phase flows when external reactor vessel cooling through flooding of the RPV occurs. The thermal hydrodynamic phenomena in an external reactor vessel are simulated using a computational fluid dynamics (CFD) technique with a phase change heat/mass transfer approach for boiling and the volume of fluid (VOF) approach for two-phase flows. The simulation results give a better understanding of the heat transfer from molten corium to the coolant outside the vessel and of the natural circulation mechanism of cooling water, boiling, and two-phase flows in this system. Also, this study provides quantitative data, such as heat flux, natural circulation flow rates, and heat transfer coefficients at various cooling water temperatures.

Copyright © 2012 by ASME



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