A new experimental investigation on local fuel-coolant interaction in a molten pool

Cheng, 2013, Characteristics of self-leveling behavior of debris beds in a series of experiments, Nucl. Eng. Technol., 45, 323, 10.5516/NET.02.2012.068 Cheng, 2014, An experimental study on local fuel–coolant interactions by delivering water into a simulated molten fuel pool, Nucl. Eng. Des., 275, 133, 10.1016/j.nucengdes.2014.05.003 Cheng, 2015, A numerical study on local fuel–coolant interactions in a simulated molten fuel pool using the SIMMER-III code, Ann. Nucl. Energy, 85, 740, 10.1016/j.anucene.2015.06.030 Cheng, 2018, A two-dimensional experimental investigation on the sloshing behavior in a water pool, Ann. Nucl. Energy, 114, 2018 Ciampichetti, 2009, Experimental and computational investigation of LBE-water interaction in LIFUS 5 facility, Nucl. Eng. Des., 239, 2468, 10.1016/j.nucengdes.2009.08.007 Huhtiniemi, 1999, Results of recent KROTOS FCI tests: alumina vs. corium melts, Nucl. Eng. Des., 189, 379, 10.1016/S0029-5493(98)00269-6 Kamiyama, 2013, Experimental study on fuel-discharge behavior through in-core coolant channels, J. Nucl. Sci. Technol., 50, 629, 10.1080/00223131.2013.785272 Kayser, 1998, Summary of the SCARABEE-N subassembly melting and propagation tests with an application to a hypothetical total instantaneous blockage in a reactor, Nucl. Sci. Eng., 128, 144, 10.13182/NSE98-A1950 Kim, 2010, Triggered steam explosions with the corium melts of various compositions in a two-dimensional interaction vessel in the TROI facility, Nucl. Technol., 176, 372, 10.13182/NT11-A13314 Kondo, 1995, Experimental study on simulated molten jet-coolant interactions, Nucl. Eng. Des., 155, 73, 10.1016/0029-5493(94)00870-5 Magallon, 2006, Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments, Nucl. Eng. Des., 236, 1998, 10.1016/j.nucengdes.2006.03.038 Maschek, 1992, Investigations of sloshing fluid motions in pools related to recriticalities in liquid-metal fast breeder reactor core meltdown accidents, Nucl. Technol., 98, 27, 10.13182/NT92-A34648 Morita, 1999, SIMMER-III applications to fuel-coolant interactions, Nucl. Eng. Des., 189, 337, 10.1016/S0029-5493(98)00267-2 Park, H.S., Yamano, N., Maruyama, Y., Moriyama, K., Yang, Y., Sugimoto, J., 1998. Study on energetic fuel-coolant interaction in the coolant injection mode of contact. In: Proc. of 6th Int. Conf. Nuclear Engineering (ICONE-6), San Diego, California, May 10–15, 1998. Sibamoto, 2002, Visualization and measurement of subcooled water jet injection into high-temperature melt by using high-frame-rate neutron radiography, Nucl. Technol., 139, 205, 10.13182/NT02-A3314 Spencer, 1994 Theofanous, 1986, An assessment of Clinch River breeder reactor core disruptive accident energetics, Nucl. Technol., 93, 215 Tobita, Y., Morita, K., Kawada, K., Niwa, H., Nonaka, N., 1999. Evaluation of CDA energetics in the prototype LMFBR with latest knowledge and tools. In: Proceedings of 7th International Conference on Nuclear Engineering(ICONE-7), Tokyo, Japan, April 19–23, 1999. Tobita, 2006, The development of SIMMER-III, an advanced computer program for LMFR safety analysis, and its application to sodium experiments, Nucl. Techonol., 153, 243 Yamano, 2009, Transient heat transfer characteristics between molten fuel and steel with steel boiling in the CABRI-TPA2 test, Nucl. Technol., 165, 145, 10.13182/NT09-A4082