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Sogabe, Joji; Suzuki, Toru; Wada, Yusaku; Tobita, Yoshiharu
Nippon Kikai Gakkai Rombunshu (Internet), 83(848), p.16-00393_1 - 16-00393_10, 2017/04
The achievement of In-Vessel Retention (IVR) of the accident consequences in an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, is effective and rational approach in enhancing the safety characteristics of sodium-cooled fast reactor. The objective of the present study is to show that the decay heat generated from the relocated fuels would be stably removed in post-accident-material-relocation/post-accident-heat-removal (PAMR/PAHR) phase, where the relocated fuels mean fuel discharged from the core into the low-pressure plenum through control-rod guide tubes, and fuel remnant in the disrupted core region (non-discharged fuel). As a result of the present assessments, it should be concluded that the stable cooling of the relocated fuels was confirmed and the prospect of IVR was obtained.
Suzuki, Toru; Sogabe, Joji; Tobita, Yoshiharu; Sakai, Takaaki*; Nakai, Ryodai
Nippon Kikai Gakkai Rombunshu (Internet), 83(848), p.16-00395_1 - 16-00395_9, 2017/04
no abstracts in English
Sogabe, Joji; Suzuki, Toru; Wada, Yusaku; Tobita, Yoshiharu
Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 7 Pages, 2016/11
Sogabe, Joji; Suzuki, Toru; Wada, Yusaku; Tobita, Yoshiharu
Dai-21-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 3 Pages, 2016/06
no abstracts in English
Suzuki, Toru; Sogabe, Joji; Tobita, Yoshiharu; Sakai, Takaaki*; Nakai, Ryodai
Dai-21-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 4 Pages, 2016/06
Suzuki, Toru; Tobita, Yoshiharu; Kawada, Kenichi; Tagami, Hirotaka; Sogabe, Joji; Matsuba, Kenichi; Ito, Kei; Ohshima, Hiroyuki
Nuclear Engineering and Technology, 47(3), p.240 - 252, 2015/04
Times Cited Count：15 Percentile：11.72(Nuclear Science & Technology)Suzuki, Toru; Tobita, Yoshiharu; Kawada, Kenichi; Tagami, Hirotaka; Sogabe, Joji; Ito, Kei
Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 10 Pages, 2014/07
Sogabe, Joji; Takata, Takashi*; Yamaguchi, Akira*; Kikuchi, Shin; Ohshima, Hiroyuki
Journal of Nuclear Science and Technology, 49(11), p.1067 - 1077, 2012/11
Times Cited Count：0 Percentile：100(Nuclear Science & Technology)Sodium water reaction (SWR) is a design basis accident of a sodium-cooled fast reactor (SFR). In a steam generator (SG) of the SFR, when a heat transfer tube fails, highly pressurized water or water vapor will leak into liquid sodium resulting in a chemical reaction between sodium and water or water vapor. The mechanisms of the SWR are complicated and have not been fully elucidated. The authors have developed a numerical code and have carried out SWR experiments of a counter-flow diffusion flame (in gas phase). In this paper, the authors perform numerical simulations based on the experimental conditions to validate two chemical reaction models. In addition, sensitivity analyses are performed for various hydration numbers and water vapor flow velocities. It is founded that hydration reaction occurs somewhat in the gas-phase reaction and that influences of the water vapor flow velocity are not negligible mainly from the viewpoint of the reaction surface location.
Yamaguchi, Akira*; Takata, Takashi*; Ohshima, Hiroyuki; Sogabe, Joji*; Deguchi, Yoshihiro*; Kikuchi, Shin
Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 8 Pages, 2010/05
Sodium-water reaction (SWR) is a design basis accident of a sodium fast reactor (SFR). A breach of the heat transfer tube in a steam generator (SG) results in contact of liquid sodium with water. The purpose of the present paper is to delineate the mechanism and process of the SWR by a counter-flow diffusion flame experiment and a numerical simulation.
Sogabe, Joji*; Yamaguchi, Akira*; Takata, Takashi*; Ohshima, Hiroyuki; Kikuchi, Shin; Deguchi, Yoshihiro*
no journal, ,
no abstracts in English
Sogabe, Joji*; Yamaguchi, Akira*; Takata, Takashi*; Ohshima, Hiroyuki; Kikuchi, Shin
no journal, ,
Evaluation of sodium-water reaction phenomena is one of important safety issues in sodium-cooled fast reactors. In this study, we have considered sodium dynamics near reaction surface based on the experimental results, including concentration distributions of sodium, water vapor, and aerosol measured in counter-flow diffusion flame experiment of sodium and water.
Sogabe, Joji; Koyama, Kazuya*; Tobita, Yoshiharu
no journal, ,
no abstracts in English
Sogabe, Joji; Suzuki, Toru; Tobita, Yoshiharu
no journal, ,
no abstracts in English
Sogabe, Joji; Wada, Yusaku; Suzuki, Toru; Tobita, Yoshiharu
no journal, ,
no abstracts in English
Sogabe, Joji; Wada, Yusaku*; Suzuki, Toru*; Tobita, Yoshiharu
no journal, ,
no abstracts in English
