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Yanagihara, Satoshi; Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Tanaka, Mitsugu
International Journal of Robotics and Automation, 18(4), p.160 - 165, 2003/12
no abstracts in English
Okoshi, Minoru; Sakai, Akihiro; Abe, Masayoshi; Tanaka, Mitsugu
IAEA-CN-87/50 (CD-ROM), p.113 - 118, 2002/12
As the result of research activities for nuclear energy utilization over 45 years, large amounts of low-level radioactive waste (LLW) are stored at Tokai Research Establishment of JAERI. In order to plan the disposal program, JAERI carried out the radiological characterization of the waste. The results show that about 34,400 tons of LLW will arise from the operation and dismantling of the facilities by the end of 2045. The total activities of beta- and gamma-radionuclides and alpha-radionuclides are about 44 PBq and 56 TBq, respectively. By using the estimated total weight and radioactivities of the waste, important radionuclides were selected from the viewpoint of safety according to the performance assessment of near surface disposal facilities. As the results, twenty-seven radionuclides including twelve alpha-ray emitting actinides were selected as the candidate important radionuclides. Those are slightly different from important radionuclides selected for commercial nuclear power plants because of materials used for facilities and so on.
Tanaka, Mitsugu; Yanagihara, Satoshi
Safe Decommissioning for Nuclear Activities, p.65 - 75, 2002/10
no abstracts in English
Tanaka, Mitsugu
Gijutsu To Keizai, (412), p.46 - 51, 2001/06
no abstracts in English
Higuchi, Hidekazu; Sato, Motoaki; Hirabayashi, Takakuni*; Tanaka, Mitsugu
Proceedings of 2nd International Conference on Safewaste 2000, Vol.1, p.314 - 322, 2000/00
no abstracts in English
Tanaka, Mitsugu; Okoshi, Minoru
Proceedings of Joint NEA/IAEA/EC Workshop on the Regulatory Aspects of Decommissioning, 3A, p.141 - 146, 1999/00
no abstracts in English
Tanaka, Mitsugu
Proc. of Int. Conf. of Dismantling of Nuclear Facilities, 1, p.54 - 64, 1998/00
no abstracts in English
Tanaka, Mitsugu
Nihon Kikai Gakkai-Shi, 100(938), 93 Pages, 1997/01
no abstracts in English
Miyasaka, Yasuhiko; Tanaka, Mitsugu
10th Pacific Basin Nuclear Conf. (10-PBNC), 2, p.1223 - 1230, 1996/00
no abstracts in English
Miyasaka, Yasuhiko; ; Tanaka, Mitsugu; Nakamura, Hisashi; ; Tachibana, Mitsuo; ; Hatakeyama, Mutsuo; ; Yoshimori, Michiro; et al.
Nihon Genshiryoku Gakkai-Shi, 38(7), p.553 - 576, 1996/00
no abstracts in English
*; Yanagihara, Satoshi; Sukegawa, Takenori; Tanaka, Mitsugu
Nihon Genshiryoku Gakkai-Shi, 33(6), p.574 - 584, 1991/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Yanagihara, Satoshi; Tanaka, Mitsugu
Energy J., Vol. 12 (Special Issue), p.135 - 148, 1991/00
no abstracts in English
G.Pratapagiri*; Yanagihara, Satoshi; Fujiki, Kazuo; J.Liederman*; Tanaka, Mitsugu
Low and Intermediate Level Radioactive Waste Management,Vol. 1, p.615 - 623, 1991/00
no abstracts in English
Yanagihara, Satoshi; *; Tanaka, Mitsugu
Nihon Genshiryoku Gakkai-Shi, 30(3), p.235 - 246, 1988/00
Times Cited Count：2 Percentile：31.38(Nuclear Science & Technology)no abstracts in English
Hoshi, Tatsuo; Tanaka, Mitsugu; Kawasaki, Minoru
Proc. 2nd Int. RILEM Symp. on Demolition Methods and Practice, p.463 - 472, 1988/00
no abstracts in English
Tanaka, Mitsugu; Yanagihara, Satoshi; Ishikawa, Michio; Kawasaki, Minoru
Proc. Int. Conf. on Decommissioning of Major Radioactive Facilities, p.25 - 31, 1988/00
no abstracts in English
Hoshi, Tatsuo; Tanaka, Mitsugu
Nihon Genshiryoku Gakkai-Shi, 29(7), p.584 - 592, 1987/07
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
Yasunaka, Hideo; ; Sukegawa, Takenori; ; Tanaka, Mitsugu
CONF-871018-Vol.2, p.4-109 - 4-116, 1987/00
no abstracts in English
; Yanagihara, Satoshi; *; Tanaka, Mitsugu
CONF-871018-Vol.2, p.5-67 - 5-78, 1987/00
no abstracts in English
Kikuchi, Hideki; Numata, Shinji; Suzuki, Kazuyuki; Wakimoto, Fumitsugu; Tanaka, Yukiyoshi
no journal, ,
Tokai Reprocess Plant (TRP) has reprocessed about 1140 tU spent nuclear fuel for 35 years. In clarification process, there are 2 kinds of valves that used under spent fuel dissolving solution environment. These valves operation data are very valuable in process handling dissolving solution because the valves are rarely used in this process. In this report, we summarize malfunctions of the valves that we have experienced until now, and explain the method of maintenance and operation management.
