Simulation of melt jet breakup experiments by JASMINE with an empirical correlation for melt particle size distribution

References

• OECD/NEA. OECD workshop on ex-vessel debris coolability summary and recommendations. Paris (France): OECD/NEA/CSNI; 2000. (NEA/CSNI/R(2000)14).
   Google Scholar
• Bürger M. Particulate debris formation by breakup of melt jets: main objectives and solution perspectives. Nucl Eng Des. 2006;236:1991–1997.
   Web of Science ®Google Scholar
• Annunziato A, Addabo C, Yerkess A, et al. FARO test L-14 on fuel-coolant interaction and quenching– comparison report. Volume I: analysis of the results – OECD/CSNI International standard problem 39. Paris (France): OECD/NEA/CSNI; 1998. (NEA/CSNI/R(97)31/Part I).
   Google Scholar
• OECD/NEA. OECD research program on fuel-coolant interaction: steam explosion resolution for nuclear applications – SERENA, final report. Paris (France): OECD/NEA/CSNI; 2007. (NEA/CSNI/R(2007)11).
   Google Scholar
• OECD/NEA. OECD/SERENA project report: summary and conclusions. Paris (France): OECD/NEA; 2015. (NEA/CSNI/R(2014)15).
   Google Scholar
• Moriyama K, Nakamura H. A strategy for the application of steam explosion codes to reactor analysis. Proceedings of Technical Meeting on Severe Accident and Accident Management; 2006; Tokyo, Japan. (CD-ROM).
   Google Scholar
• Meignen R, Picchi S, Lamome J, et al. The challenges of modeling fuel-coolant interaction. Part I – premixing. Nucl Eng Des. 2014;280:511–527.
   Web of Science ®Google Scholar
• Corradini ML, El-Beshbeeshy M, Nilsuwankosit S, et al. Fuel fragmentation model advances using TEXAS-V. In: Akiyama M, Yamano N, Sugimoto J, editors. Proceedings of the OECD/CSNI Specialists Meeting on Fuel-Coolant Interactions; 1997 May 19–21; Tokai-mura, Japan (JAERI-Conf 97-011, NEA/CSNI/R(97)26) (Part II). Tokai (Japan): Japan Atomic Energy Research Institute; 1997. p. 733–748.
   Google Scholar
• Moriyama K, Maruyama Y, Nakamura H. Steam explosion simulation code JASMINE v.3 user's guide. Tokai (Japan): Japan Atomic Energy Agency; 2008. (JAEA-Data/Code 2008-014).
   Google Scholar
• Schröder M. Three-dimensional modeling and simulation of vapor explosions in light water reactors [dissertation]. IKE, Universität Stuttgart; 2012.
   Google Scholar
• Chen RH, Corradini ML, Su GH, et al. Analysis of KROTOS steam explosion experiments using the improved fuel-coolant-interaction code TEXAS-VI. Nucl Sci Eng. 2013;174:46–59.
   Web of Science ®Google Scholar
• Moriyama K, Maruyama Y, Usami T, et al. Coarse break-up of a stream of oxide and steel melt in a water pool. Tokai (Japan): Japan Atomic Energy Research Institute; 2005. (JAERI-Research 2005-017).
   Google Scholar
• Magallon D. Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments. Nucl Eng Des. 2006;236:1998–2009.
   Web of Science ®Google Scholar
• Liu C, Theofanous TG. Film boiling on spheres in single- and two-phase flows. Idaho Falls (ID): US Department of Energy; 1996. (DOE/ER/12933-3, DOE/ID-10499).
   Google Scholar
• Magallon D, Huhtiniemi I, Hohmann H. Lessons learnt from FARO/TERMOS corium melt quenching experiments. Nucl Eng Des. 1999;189:223–238.
   Web of Science ®Google Scholar
• Magallon D, Huhtiniemi I. Corium melt quenching tests at low pressure and subcooled water in FARO. Nucl Eng Des. 2001;204:369–376.
   Web of Science ®Google Scholar
• Kaiser A, Schütz W, Will H. PREMIX: experiments PM12–PM18 to investigate the mixing of a hot melt with water. Karlsruhe (Germany): Forschungszentrum Karlsruhe; 2001. (FZKA 6380).
   Google Scholar
• Hinds WC. Aerosol technology. New York (NY): Wiley; 1982.
   Google Scholar
• Taylor GI. The dispersion of jets of metals of low melting point in water. In: Batchelor GK, editor. The scientific papers of Sir Geoffrey Ingram Taylor. Vol. 3, Aerodynamics and the mechanics of projectiles and explosions. Cambridge: Cambridge University Press; 1963. p. 304–305.
   Google Scholar
• Saito M, Sato K, Imahori S. Experimental study on penetration behaviors of water jet into freon-11 and liquid nitrogen. ANS Proceedings of the National Heat Transfer Conference, Vol. 3; 1988 July 24–27; Houston (TX). La Grange Park (IL): ANS; 1988. p. 173–183.
   Google Scholar
• Iman RL, Shortencarier MJ. A FORTRAN 77 program and user's guide for the generation of Latin hypercube and random samples for use with computer models. US Nuclear Regulatory Commission; 1984. (NUREG/CR-3624,SAND83-2365).
   Google Scholar
• Dinh TN, Dinh AT, Nourgaliev RR, et al. Investigation of film boiling thermal hydraulics under FCI conditions: results of analyses and numerical study. Nucl Eng Des. 1999;189:251–272.
   Web of Science ®Google Scholar
• Dombrovsky L. Large-cell model of radiation heat transfer in multiphase flows typical for fuel-coolant interaction. Int J Heat Mass Transf. 2007;50:3401–3410.
   Web of Science ®Google Scholar
• Hagrman DT. SCDAP/RELAP5/MOD3.1 code manual. Vol. 4: MATPRO – A library of materials properties for light-water-reactor accident analysis. US Nuclear Regulatory Commission; 1993. (NUREG/CR-6150, EGG-2720).
   Google Scholar
• Moriyama K, Nakamura H, Maruyama Y. Analytical tool development for coarse break-up of a molten jet in a deep water pool. Nucl Eng Des. 2006;236:2010–2025.
   Web of Science ®Google Scholar
• Annunziato A, Addabbo C, Magallon D. FARO test L-28 quick look report. Ispra (Italy): European Commission Joint Research Centre; 1999. (TN I.99.74).
   Google Scholar
• Hwang G, Kaviany M, Moriyama K, et al. Ex-vessel corium-melt cooling in water pool: roles of melt superheat and sintering in sediment. Nucl Eng Des. 2016. [In review].
   Web of Science ®Google Scholar
• Kim CS. Thermophysical properties of stainless steels. Lemont (IL): Argonne National Laboratory; 1975. (ANL-75-55).
   Google Scholar
• The Japan Society of Mechanical Engineers (JSME), editor. JSME data book: thermophysical properties of fluids. Tokyo (Japan): The Japan Society of Mechanical Engineers; 1994.
   Google Scholar