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Johnson, M.*; Delacroix, J.*; Journeau, C.*; Brayer, C.*; Clavier, R.*; Montazel, A.*; Pluyette, E.*; Matsuba, Kenichi; Emura, Yuki; Kamiyama, Kenji
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 8 Pages, 2022/04
Fuel-coolant interactions in the event of molten fuel discharge to the lower plenum of a sodium cooled fast reactor is under investigation as part of a French-Japanese experimental collaboration on severe accidents. The MELT facility enables the X-ray visualisation of the quenching of molten core material jets in sodium at kilogram-scale. The SERUA facility, currently under preparation, is presented for the investigation of boiling heat transfer at elevated melt-coolant interface temperatures. In this article, the status of the collaboration using these facilities is presented.
Horiguchi, Naoki; Yoshida, Hiroyuki; Yamamura, Sota*; Fujiwara, Kota*; Kaneko, Akiko*; Abe, Yutaka*
Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 14 Pages, 2022/03
Suzuki, Takayuki*; Yoshida, Hiroyuki; Horiguchi, Naoki; Yamamura, Sota*; Abe, Yutaka*
Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 7 Pages, 2020/08
Hotta, Akitoshi*; Morita, Akinobu*; Kajimoto, Mitsuhiro*; Maruyama, Yu
Nihon Genshiryoku Gakkai Wabun Rombunshi, 16(3), p.139 - 152, 2017/09
Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Annals of Nuclear Energy, 85, p.740 - 752, 2015/11
Times Cited Count：25 Percentile：91.11(Nuclear Science & Technology)Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 9 Pages, 2015/05
Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Science and Technology of Nuclear Installations, 2015, p.964327_1 - 964327_14, 2015/00
Times Cited Count：3 Percentile：27.78(Nuclear Science & Technology)Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu*
Nuclear Engineering and Design, 236(19-21), p.2010 - 2025, 2006/10
Times Cited Count：22 Percentile：82.01(Nuclear Science & Technology)A computer code JASMINE-pre was developed for the prediction of premixing conditions of fuel-coolant interactions and the debris bed formation behavior relevant to severe accidents of light water reactors. JASMINE-pre consists of three melt component models: melt jet, melt particles and melt pool, coupled with a two-phase flow model derived from the ACE-3D code developed at JAERI. Simulations of the FARO corium quenching experiments with a saturated water pool and with a subcooled water pool were performed with JASMINE-pre and 
. JASMINE-pre reproduced the pressurization and fragmentation behaviors observed in the experiments with a reasonable accuracy. The results by pmjet showed qualitatively the same trend with JASMINE-pre in the fragmentation behavior.
21, 1997, Tokai-mura, Japan*; ; Sugimoto, Jun
JAERI-Conf 97-011, 829 Pages, 1998/01
no abstracts in English
Fuketa, Toyoshi
Joki Bakuhatsu No Shinario (Joki Bakuhatsu No Dorikigaku Kenkyu Gurupu Kenkyukai Hokokusho), 0, p.27 - 38, 1996/00
no abstracts in English
Fuketa, Toyoshi
Proc. of Seminar on the Vapor Explosions in Nuclear Power Safety, 0, p.121 - 133, 1996/00
no abstracts in English
Fuketa, Toyoshi; Ishijima, Kiyomi; ; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo
JAERI-Research 95-077, 28 Pages, 1995/10
JAERI-Research-95-077.pdf:2.49MB
no abstracts in English
V.Georgevich*; R.P.Taleyarkhan*; S.H.Kim*; Fuketa, Toyoshi; Soyama, Kazuhiko; Ishijima, Kiyomi
ORNL/TM-12956, 0, 117 Pages, 1995/06
no abstracts in English
Fuketa, Toyoshi; Ishijima, Kiyomi; Tanzawa, Sadamitsu; Nakamura, Takehiko; Sasajima, Hideo; Kashima, Yoichi; ;
JAERI-Research 95-005, 53 Pages, 1995/01
JAERI-Research-95-005.pdf:1.96MB
no abstracts in English
Fuketa, Toyoshi;
Nucl. Eng. Des., 146, p.181 - 194, 1994/00
Times Cited Count：9 Percentile：63.73(Nuclear Science & Technology)no abstracts in English
Fuketa, Toyoshi; Yamano, N.; *
Proc. of the CSNI Specialists Meeting on Fuel-Coolant Interactions: NUREG/CP-0127,NEA/CSNI/R (93)8, p.282 - 295, 1993/00
no abstracts in English
Fuketa, Toyoshi;
Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5,Vol. 3, p.753 - 761, 1992/00
no abstracts in English
; ;
JAERI-M 84-235, 44 Pages, 1985/01
no abstracts in English
*; *;
Journal of Nuclear Science and Technology, 22(9), p.742 - 754, 1985/00
Times Cited Count：17 Percentile：85.48(Nuclear Science & Technology)no abstracts in English
-HO System);
JAERI-M 8035, 94 Pages, 1979/01
no abstracts in English
