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Technical Papers

Numerical Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR After Severe Accident

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Pages 115-130 | Received 27 Apr 2018, Accepted 17 Aug 2018, Published online: 29 Oct 2018

References

  • G. W. MITCHELL, C. A. OTTINGER, and H. MEISTER, “Coolability of UO2 with Downward Heat Removal the D10 Experiment,” [LMFBR]. No. SAND-84-1144C; CONF-841174-2. Sandia National Labs., Albuquerque, NM (1984).
  • K. VIEROW et al., “Severe Accident Analysis of a PWR Station Blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 Codes,” Nucl. Eng. Des., 234, 1, 129 (2004); https://doi.org/10.1016/j.nucengdes.2004.09.001.
  • R. GAUNT, “MELCOR Computer Code Manuals: Reference Manuals Version 1.8.5,” Vol. 2, Rev. 2., NUREG/CR-6119, U.S. Nuclear Regulatory Commission, Washington, DC (2000). 81, 2000.
  • G. BERTHOUD and M. VALETTE, “Development of a Multidimensional Model for the Premixing Phase of a Fuel-Coolant Interaction,” Nucl. Eng. Des., 149, 1–3, 409 (1994); https://doi.org/10.1016/0029-5493(94)90306-9.
  • G. BERTHOUD, “Models and Validation of Particulate Debris Coolability with the Code MC3D-REPO,” Nucl. Eng. Des., 236, 19–21, 2135 (2006); https://doi.org/10.1016/j.nucengdes.2006.03.060.
  • S. RAHMAN, “Coolability of Corium Debris Under Severe Accident Conditions in Light Water Reactors.” Uni Stuttgart - Universitätsbibliothek (2013).
  • M. BUCK, “Modelling of the Late Phase of core Degradation in Light Water Reactors.” Uni Stuttgart - Universitätsbibliothek (2007).
  • U. ENERGIESYSTEME and W. SCHMIDT. “Influence of Multidimensionality and Interfacial Friction on the Coolability of Fragmented Corium.” Uni Stuttgart - Universitätsbibliothek (2004).
  • E. TAKASUO, V. HOVI, and M. ILVONEN, “Applications and Development of the PORFLO 3D Code in Nuclear Power Plant Thermal Hydraulics,” 2012 20th Int. Conf. Nuclear Engineering and the ASME 2012 Power Conf., American Society of Mechanical Engineers, Anaheim, CA, July 30–August 3, (2011).
  • S. YAKUSH, P. KUDINOV, and T.-N. DINH, “Multiscale Simulations of Self-Organization Phenomena in the Formation and Coolability of Corium Debris Bed,” Proc. 13th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-13), Paper N13P1143, Kanazawa City, Japan, September 27–October 2, (2009).
  • F. PAROZZI et al., “Fast Running Models of Molten Corium Coolability for Safety Analysis of Nuclear Reactors,” Congresso Nazionale ATI–Domus de Maria (CA), Vol. 13 (2010).
  • D. K. WARINNER and D. H. Y. CHAO, “Thermal Analysis of a Six-Channel Heat-Generating Blockage in an LMFBR,” CONF-801002–15, Argonne National Laboratory (1980).
  • O. KAZUHIRO et al., Comparison and Evaluation on Post-Accident Residual Heat Removal Characteristics of Different Reactor Core with Different Fuel, Mitsubishi Heavy Industries, Ltd. (2000).
  • A. K. STUBOS and J.-M. BUCHLIN, “Vapour Channels in Boiling, Unconstricted Particle Beds—Effect on the Dryout Heat Flux,” Int. J. Multiph. Flow, 20, 1, 131 (1994); https://doi.org/10.1016/0301-9322(94)90010-8.

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