REFERENCES
- M. L. CORRADINI, B. J. KIM and M. D. OH, “Vapor Explosions in Light Water Reactors: A Review of Theory and Modeling,” Prog. Nucl. Energy, 22, 1, 1 (1988).
- K. MATSUMURA and H. NARIAI, “Self-Triggering Mechanism of Vapor Explosions for a Molten Tin and Water System,” J. Nucl. Sci.Technol., 33, 4, 298 (1996).
- D. E. MITCHELL, M. L. CORRADINI and W. W. TAR-BELL, “Intermediate Scale Steam Explosion Phenomena: Experiments and Analysis,” NUREG/CR-2145, SAND81-0124, Sandia National Laboratories (1981).
- D. Magallon and I. HUHTINIEMI, “Corium Melt Quenching Tests at Low Pressure and Subcooled Water in FARO,” Nucl. Eng. Des., 204, 369 (2001).
- I. HUHTINIEMI and D. MAGALLON, “Insight into Steam Explosions with Corium Melts in KROTOS,” Nucl. Eng. Des., 204, 391 (2001).
- R. MEIGNEN and D. MAGALLON, “Comparative Review of FCI Computer Models Used in the OECD-SERENA Program,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP-05), Seoul, Korea, May 15-9, 2005.
- D. MAGALLON, “Status and Prospects of Resolution of the Vapor Explosion Issue in Light Water Reactors,” Nucl. Eng. Technol., 41, 5, 603 (2009).
- T. N. DINH, “Material Property Effect in Steam Explosion Energetics: Revisited,” Proc.l2th Int. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, Pennsylvania, September 30-October 4, 2007, American Nuclear Society (2007).
- T. N. DINH et al., “An Assessment of Steam Explosion Potential in Molten-Fuel-Coolant Interaction Experiments,” Proc. ICONE-6, San Diego, California, May 1998.
- H. D. KIM et al., “Investigations on the Resolution of Severe Accident Issues for Korean Nuclear Power Plants,” Nucl. Eng. Technol., 41, 5, 617 (2009).
- J. H. KIM et al., “A Study on Intermediate Scale Steam Explosion Experiments with Zirconia and Corium Melt,” Proc. Int. Congress on Advanced Nuclear Power Plant (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002).
- J. H. KIM et al., “An Effect of Corium Composition Variations on Occurrence of a Spontaneous Steam Explosion in the TROI Experiments,” presented at Proc. 6th Int. Conf. Nuclear Thermal Hydraulics, Operations and Safety Experiments (NUTHOS-6), Nara, Japan, October 4-8, 2004.
- J. H. KIM et al., “The Influence of Variations in the Water Depth and Melt Composition on a Spontaneous Steam Explosion in the TROI Experiments,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP '04), Pittsburgh, Pennsylvania, June 13-17, 2004, American Nuclear Society (2004) 14. J. H. Kim et al., “Triggered Steam Explosions with the Corium Melts of Various Compositions in a Two Dimensional Interaction Vessel in the TROI Facility,” Nucl. Eng. Technol., 176, 372 (2011).
- J. H. KIM et al., “Results of the Triggered TROI Steam Explosion Experiments,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP'06), Reno, Nevada, June 4-8, 2006, American Nuclear Society (2006).
- J. H. KIM et al., “Triggered Steam Explosions with the Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI Facility,” Nucl. Technol., 169, 239 (2010).
- V. I. ALEKSANDROV et al., “Synthesis and Crystal Growth of Refractory Materials by RF Melting in a Cold Container, Chapter 6,” Current Topics In Materials Science, Vol. 1, E. KALDIS, Ed., North Holland Publishing Company (1978).
- I. HUHTINIEMI, D. MAGALLON, and H. HOHMANN, “Results of Recent KROTOS FCI Tests: Alumina Versus Co-rium Melts,” Nucl. Eng. Des., 189, 379 (1999).
- N. YMANAO et al., “Phenomenological Studies on Melt-Coolant Interactions in theALPHA Program,” Nucl. Eng. Des., 155, 369 (1995).
- D. H. CHO, D. R. ARMSTRONG, and W. H. GUNTHER, “Experiments on Interactions between Zirconium-Containing Melt and Water,” NUREG/CR-5372, Argonne National Laboratory (1998).
- D. MAGALLON, “Charateristics of Corium Debris Bed Generated in Large-Scale Fuel-Coolant Interaction Experiments,” Nucl. Eng. Des., 236, 1998 (2006).
- K. H. KANG et al., “Experimental Investigations on In-Vessel Corium Retention through Inherent Gap Cooling Mechanisms,” J. Nucl. Sci.Technol., 43, 12, 1490 (2006).
- K. H. KANG et al., “Synthesis Analyses of the LAVA Experimental Results on In-Vessel Corium Retention through Gap Cooling,” KAERI/TR-1805/2001 (2001).
- “SCDAP/RELAP5/MOD2 Code Manual, Vol. 4; MATPRO-A Library of Materials Properties for Light Water Reactor Accident Analysis,” NUREG/CR-52.3, EGG-2555 (1990).