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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Akasaka, Hiromi; Takano, Shoji; Sato, Tomoki; Kawamata, Yoichi
Heisei-18-Nendo Nagoya Daigaku Sogo Gijutsu Kenkyukai Kairo, Keisoku, Seigyo Gijutsu Kenkyukai Hokokushu, p.106 - 109, 2007/03
no abstracts in English
Akasaka, Hiromi; Takano, Shoji; Kawamata, Yoichi
Dai-17-Kai Bunshi Kagaku Kenkyusho Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2006/03
no abstracts in English
Akasaka, Hiromi; Takano, Shoji*; Kawamata, Yoichi; Yonekawa, Izuru
Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03
no abstracts in English
Takano, Shoji*; Totsuka, Toshiyuki; Yonekawa, Izuru
KEK Proceedings 2003-16 (CD-ROM), 4 Pages, 2004/02
no abstracts in English
Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Yonekawa, Izuru
Fusion Engineering and Design, 60(3), p.409 - 414, 2002/06
Times Cited Count：2 Percentile：17.03(Nuclear Science & Technology)no abstracts in English
Takano, Shoji*; Akasaka, Hiromi; Totsuka, Toshiyuki; Yonekawa, Izuru
NIFS-MEMO-36, p.443 - 446, 2002/06
no abstracts in English
Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Totsuka, Toshiyuki; Yonekawa, Izuru; Kurihara, Kenichi; Kimura, Toyoaki
JAERI-Tech 2001-087, 109 Pages, 2002/01
JAERI-Tech-2001-087.pdf:6.83MB
The JT-60 discharge control system had been used since the start of JT-60 experiment in 1985, was renewed in March, 2001. The new system consists of a UNIX workstation and a VME-bus system, and features a distributed control system. The workstation performs message communication with a VME-bus system and controllers of JT-60 sub-systems and data processing for discharge control. The VME-bus system performs discharge sequence control. The replacement has improved the control function and reliability of the discharge control system and also has provided sufficient performance necessary for future modifications of JT-60. The new system has been running successfully since April 2001. The data acquisition speed was confirmed to be twice faster than the previous one. This report describes major functions of the discharge control system, technical ideas for developing the system and results of the initial operation in detail.
Yonekawa, Izuru; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Kurihara, Kenichi
Fusion Engineering and Design, 48(1-2), p.17 - 23, 2000/08
Times Cited Count：3 Percentile：26.42(Nuclear Science & Technology)no abstracts in English
; Muromura, Tadasumi; Takano, Hideki; Matsuura, Shojiro
Nuclear Technology, 107, p.182 - 192, 1994/08
Times Cited Count：101 Percentile：98.68(Nuclear Science & Technology)no abstracts in English
Kataoka, Shoji; Takano, Masato; Sato, Fuminori; Saito, Yasuo
no journal, ,
no abstracts in English
Kataoka, Shoji; Takano, Masato; Nagayama, Mineo; Kano, Yoshiharu*; Suzuki, Tatsuya*; Miyabe, Shinsuke*; Sakuma, Takashi*; Shirozu, Hidetomo
no journal, ,
no abstracts in English
Tsunoda, Hiroki; Kataoka, Shoji; Takano, Masato; Sato, Fuminori
no journal, ,
The Low Active Waste Treatment Development Facility (LWTF) at the Tokai Reprocessing Plant (TRP) is a facility to treat low radioactive liquid and solid wastes generated from the reprocessing plant. The liquid wastes to be treated at the LWTF are low radioactive concentrated liquid waste and phosphate liquid waste, which are planned to be cemented solidified. The low radioactive concentrated liquid waste will be separated into slurry liquid waste and carbonate liquid waste by the existing nuclide separation facility and the newly constructed nitrate root decomposition facility, and then cement solidified. Currently, studies and designs are underway for the introduction of a nitrate root decomposition facility and a cement solidification facility. This report describes the results of full-scale kneading tests for cement solidification, which confirmed that the carbonate, slurry, and phosphate wastes hardened by the next day, did not generate floating water, and had sufficient compressive strength.
