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Shibanuma, Kiyoshi
Nihon Genshiryoku Gakkai-Shi, 47(11), p.761 - 767, 2005/11
In-vessel components such as blanket and divertor of the fusion reactor are activated by neutron produced during fusion reaction. Gamma radiation will be about 500 MGy/h in maximum after fusion reaction. When the components are failed or troubled in the vessel, the maintenence has to be carried out by the robot because the human cannot be close inside the vessel. The required functions and present R&D status of the typical robots applied to ITER are introduced as examples of robots maintaining the in-vessel components of the fusion reactor.
Teshigawara, Makoto; Aizawa, Hideyuki; Harada, Masahide; Kinoshita, Hidetaka; Meigo, Shinichiro; Maekawa, Fujio; Kaminaga, Masanori; Kato, Takashi; Ikeda, Yujiro
JAERI-Tech 2005-029, 24 Pages, 2005/05
JAERI-Tech-2005-029.pdf:3.38MB
This report introduces the present design status of remote-handling devices for activated and used components such as moderator and reflector in a spallation neutron source of the Material and Life Science Facility (MLF) at J-PARC. The design concept and maintenance scenario are also mentioned. A key maintenance scenario adopts that the used components should be taken out from the MLF to the other storage facility after the volume reduction of them. Almost full remote handling is available to the maintenance work except for the connection/disconnection pipes of the cooling water. Total six remote handling devices are used for moderator-reflector maintenance. They are also available to the proton beam window and muon target maintenance. Maintenance scenario is separated into two works. One is to replace used components to new ones during beam-stop and the other is dispose used components during beam operation. Required period of replacement work is estimated to be 
15 days, on the other hand, the disposal work is 26 days after dry up work (30 days), respectively.
Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka
JAERI-Tech 2004-071, 85 Pages, 2005/02
JAERI-Tech-2004-071.pdf:4.81MB
To facilitate easy maintainability, the ITER divertor is divided into 60 cassettes, which are transported for replacement using the remote equipments. The cassette of 25 tons has to be transported and installed with a positioning accuracy less than 2 mm in the limited space under the intense gamma radiation field. Based on these requirements, the following design and tests were performed. (1) Link mechanism was studied to apply to the transportation. A compact mechanism with links is designed through the optimization of the link angle taking account of space requirement and force efficiency. The lifting capacity of 30 tons has been demonstrated. (2) Compact link mechanism was also studied to apply for locking of the cassette. The final positioning accuracy of 0.03 mm for installation from the initial positioning error of 5 mm has been demonstrated. (3) Sensor-based control of the remote equipment was tested using simple sensors. It is found that the positioning accuracy of 0.16 mm has been achieved and this value is sufficient.
Oka, Kiyoshi; Shibanuma, Kiyoshi
JAERI-Tech 2003-004, 57 Pages, 2003/03
JAERI-Tech-2003-004.pdf:2.36MB
Cesium is required in order to generate a stable negative ion of hydrogen in an ion source of the neutral beam injector (NBI), which is one of the plasma-heating devices for International Thermonuclear Experimental Reactor (ITER). After long time operation of NBI, the cesium deposits to the insulators supporting the electrode. Due to the deterioration of the insulation resistance, the continuous operation of the NBI will be difficult. In addition, the NBI device is activated by neutron from D-T plasma, so that a periodic removal and cleaning of the cesium on the insulators by remote handling is required. A study of the cesium removal scenario and device is therefore required considering remote handling. In this report, a cesium removal procedure and conceptual design of the cesium removal device using laser ablation technique are studied, and the feasibility of laser ablation is shown.
Kakudate, Satoshi; Shibanuma, Kiyoshi
Fusion Engineering and Design, 65(1), p.133 - 140, 2003/01
Times Cited Count：11 Percentile：59.38(Nuclear Science & Technology)no abstracts in English
Honda, Tsutomu*; Hattori, Yukiya*; Holloway, C.*; Martin, E.*; Matsumoto, Yasuhiro*; Matsunobu, Takashi*; Suzuki, Toshiyuki*; Tesini, A.*; Baulo, V.*; Haange, R.*; et al.
Fusion Engineering and Design, 63-64, p.507 - 518, 2002/12
Times Cited Count：16 Percentile：69.83(Nuclear Science & Technology)The requirement to reduce the construction cost for ITER as compared with the 1998 ITER design, has led to a reduction in the size of the ITER machine and a number of design changes which have an impact on the remote maintenance of ITER. Major components to be considered for remote handling (RH) include the divertor cassettes, shield blanket modules, neutral beamline components, as well as in-port components, which are integrated with the port shield plug such as auxiliary heating equipment, limiters and test blanket modules. The design of the following equipment has been adapted for the smaller machine with reduced access space for the RH equipment: the RH equipment used for the in-vessel RH operationsto be deployed from the casks, the RH equipment that is used to remove the in-port assemblies (port plugs), as well as the remotely operated casks, which can be attached to and removed from vacuum vessel ports by using double -door systems. Defective components are loaded in transfer casks and moved to the hot cell facility by means of a remotely-operated air floatation system attached underneath the cask, where they dock against identical port interfaces and unload the component for remote refurbishment and/or waste storage.
Kakudate, Satoshi; Shibanuma, Kiyoshi
Kensa Gijutsu, 7(11), p.28 - 33, 2002/11
no abstracts in English
Ise, Hideo*; Izaki, Makoto*; Oishi, Haruo*; Mori, Seiji*; Ako, Kentaro*; Moriyama, Hisashi*; Kagaya, Hiroaki*; Kobayashi, Masami*; Taguchi, Ko*; Shibanuma, Kiyoshi
FAPIG, (159), p.10 - 14, 2001/11
no abstracts in English
Oka, Kiyoshi; Tada, Eisuke
JAERI-Tech 99-055, 138 Pages, 1999/08
no abstracts in English
*; Obara, Kenjiro; Tada, Eisuke; Morita, Yosuke; Yagi, Toshiaki; *
JAERI-Tech 99-029, 36 Pages, 1999/03
no abstracts in English
Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; Yagi, Toshiaki; Morita, Yosuke
J. Robot. Mechatron., 10(2), p.121 - 132, 1998/00
no abstracts in English
Nakahira, Masataka; *; *; Koizumi, Koichi
J. Robot. Mechatron., 10(2), p.116 - 120, 1998/00
no abstracts in English
Obara, Kenjiro; Kakudate, Satoshi; Nakahira, Masataka; *
J. Robot. Mechatron., 10(2), p.96 - 103, 1998/00
no abstracts in English
Oka, Kiyoshi; Obara, Kenjiro; Kakudate, Satoshi; *; *; Morita, Yosuke
Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.69 - 82, 1997/01
no abstracts in English
Tada, Eisuke; Shibanuma, Kiyoshi
Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.21 - 28, 1997/01
no abstracts in English
Nakahira, Masataka; Oka, Kiyoshi; Kakudate, Satoshi; *; *; Tada, Eisuke; Shibanuma, Kiyoshi; Matsuhira, Nobuto*; Haange, R.*
Fusion Technology 1996, 0, p.1653 - 1656, 1997/00
no abstracts in English
Tanaka, Shigeru; Ohara, Yoshihiro; Akiba, Masato; Araki, Masanori; Hanada, Masaya; Inoue, Takashi; Mizuno, Makoto; Okumura, Yoshikazu; Seki, Masahiro; Watanabe, Kazuhiro; et al.
Fusion Engineering and Design, 18, p.507 - 515, 1991/00
Times Cited Count：2 Percentile：31.89(Nuclear Science & Technology)no abstracts in English
; *; ; ; *; *; *; *; *; *; et al.
JAERI-M 85-078, 207 Pages, 1985/07
no abstracts in English
;
JAERI-M 84-233, 167 Pages, 1985/01
no abstracts in English
; ; ; Tone, Tatsuzo; *; *; *; *
Robotics and Remote Handling in Hostile Environments,Proc.1984 National Topical Meeting, p.289 - 298, 1984/00
no abstracts in English
Kakudate, Satoshi; Takeda, Nobukazu; Matsuhira, Nabuto*; Senda, Ikuo*
no journal, ,
no abstracts in English
