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Journal Articles

Intelligible seminar of fusion reactors, 10; Remote maintenance robot for in-vessel components, Advanced robot technology for handling large-heavy components with high positioning accuracy

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.

JAEA Reports

Remote handling design for moderator-reflector maintenance in JSNS

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 $$sim$$15 days, on the other hand, the disposal work is $$sim$$26 days after dry up work ($$sim$$30 days), respectively.

JAEA Reports

Research and development of remote maintenance equipment for ITER divertor maintenance

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.

JAEA Reports

Conceptual design of cesium removal device for ITER NBI maintenance

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.

Journal Articles

Rail deployment and storage procedure and test for ITER blanket remote maintenance

Kakudate, Satoshi; Shibanuma, Kiyoshi

Fusion Engineering and Design, 65(1), p.133 - 140, 2003/01

 Times Cited Count:11 Percentile:61.24(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Remote handling systems for ITER

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:71.53(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.

Journal Articles

Remote maintenance technology for ITER

Kakudate, Satoshi; Shibanuma, Kiyoshi

Kensa Gijutsu, 7(11), p.28 - 33, 2002/11

no abstracts in English

Journal Articles

Development of port plug handling tractor for ITER

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

JAEA Reports

Design of remote handling equipment for the ITER NBI

Oka, Kiyoshi; Tada, Eisuke

JAERI-Tech 99-055, 138 Pages, 1999/08

JAERI-Tech-99-055.pdf:4.49MB

no abstracts in English

JAEA Reports

Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER, 2

*; Obara, Kenjiro; Tada, Eisuke; Morita, Yosuke; Yagi, Toshiaki; *

JAERI-Tech 99-029, 36 Pages, 1999/03

JAERI-Tech-99-029.pdf:3.25MB

no abstracts in English

Journal Articles

Development of radiation hardness components for ITER remote maintenance

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; Yagi, Toshiaki; Morita, Yosuke

J. Robot. Mechatron., 10(2), p.121 - 132, 1998/00

no abstracts in English

Journal Articles

Development of thick wall welding and cutting tools for ITER

Nakahira, Masataka; *; *; Koizumi, Koichi

J. Robot. Mechatron., 10(2), p.116 - 120, 1998/00

no abstracts in English

Journal Articles

Development of ITER in-vessel viewing and metrology systems

Obara, Kenjiro; Kakudate, Satoshi; Nakahira, Masataka; *

J. Robot. Mechatron., 10(2), p.96 - 103, 1998/00

no abstracts in English

Journal Articles

Development of radiation hard components for remote maintenance

Oka, Kiyoshi; Obara, Kenjiro; Kakudate, Satoshi; *; *; Morita, Yosuke

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.69 - 82, 1997/01

no abstracts in English

Journal Articles

Remote maintenance development for ITER

Tada, Eisuke; Shibanuma, Kiyoshi

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.21 - 28, 1997/01

no abstracts in English

Journal Articles

Development of an end-effector for ITER blanket module handling

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

Journal Articles

Maintenance of neutral beam injectors for ITER; Japanese proposal

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:32.61(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,Phase Two A,Part 2 Chapter VI:Maintainability

; *; ; ; *; *; *; *; *; *; et al.

JAERI-M 85-078, 207 Pages, 1985/07

JAERI-M-85-078.pdf:5.28MB

no abstracts in English

JAEA Reports

Journal Articles

Remote maintenance design for fusion experimental reactor(FER)

; ; ; Tone, Tatsuzo; *; *; *; *

Robotics and Remote Handling in Hostile Environments,Proc.1984 National Topical Meeting, p.289 - 298, 1984/00

no abstracts in English

Oral presentation

Progress of technology development regarding remote maintenance robot for ITER

Kakudate, Satoshi; Takeda, Nobukazu; Matsuhira, Nabuto*; Senda, Ikuo*

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)