Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
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：26 Percentile：90.65(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：6 Percentile：45.92(Nuclear Science & Technology)Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu*
Nuclear Engineering and Design, 236(19-21), p.2010 - 2025, 2006/10
Times Cited Count：23 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.
Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu
Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 18 Pages, 2004/10
A steam explosion simulation code JASMINE is under development at JAERI for the assessment of steam explosion impacts on the integrity of containment vessel during severe accidents in light water reactors. Selected alumina and corium steam explosion experiments, KROTOS-44, 42, 37 and FARO-L33 were simulated with JASMINE code. The experimentally observed difference of the steam explosion intensity with the two materials, alumina and corium, was reproduced in the simulations without changing the model parameters related to the fine fragmentation process, but based on the difference in the premixing behavior predicted by the simulations. The simulation of corium experiments showed more fraction of the melt droplets frozen during premixing, as well as more void fraction, and those two points were likely to be the primary reasons of weak interactions in corium experiments.
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：63.36(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：86.32(Nuclear Science & Technology)no abstracts in English
