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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：17 Percentile：70.66(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.
Yoshida, Hiroshi; Glugla, M.*; Hayashi, Takumi; L
sser, R.*; Murdoch, D.*; Nishi, Masataka; Haange, R.*
Fusion Engineering and Design, 61-62, p.513 - 523, 2002/11
Times Cited Count：29 Percentile：84.22(Nuclear Science & Technology)ITER tritium plant is composed of tokamak fuel cycle systems, tritium confinement and detritation systems. The tokamak fuel cycle systems, composed of various tritium sumsystems such as vacuum vessel cleaning gas processing, tokamak exhaust processing, hydrogen isotope separation, fuel storage, mixing and delivery, and external tritium receiving and long-term storage, has been designed to meet not only ITER operation scenarios but safety requirements (minimization of equipment tritium inventory and reduction of environmental tritium release at different off-normal events and accident scenarios). Multiple confinement design was employed because tritium easily permeates through metals (at 
150 
C) and plastics (at ambient temperature) and mixed with moisture in room air. That is, tritium process equipment and piping are designed to be the primary confinement barrier, and the process equipments (tritium inventory 1 g) are surrounded by the secondary confinement barrier such as a glovebox. Tritium process rooms, which contains these facilities, form the tertiary confinement barrier, and equipped with emergency isolation valves in the heating ventillation and air conditioning ducts as well as atmosphere detritiation systems. This confinement approach has been applied to tokamak building, tritium building, and hotcell and radwaste building.
Guillemet, L.*; Jager, B.*; Haange, R.*; Hamada, Kazuya; Hara, Eiji*; Kalinin, G.*; Kato, Takashi; Millet, F.*; Shatil, N.*
Proceedings of 19th International Cryogenic Engineering Conference (ICEC-19), p.105 - 108, 2002/07
Japan Atomic Energy Research Institute has designed a ITER cryoplant and cryo-distribution in the international collaboration. The ITER cryoplant that will be the largest cryogenic system for the Fusion facility in the world, is designed to be stable in operation despite the pulsed nature of heat deposition in the magnet system. The refrigeration capacity of cryoplant is 48 kW at 4.5 K of refrigeration power and 0.16 kg/s of supercritical helium supply. In the cryoplant, a supercritical helium pump and a cold compressor is applied, based on the successful achievement of cryogenic system for the ITER central solenoid model coil.
Kakudate, Satoshi; Oka, Kiyoshi; Yoshimi, Takashi*; Hiyama, Masayuki; Taguchi, Ko*; Shibanuma, Kiyoshi; Koizumi, Koichi; Matsumoto, Yasuhiro*; Honda, Tsutomu*; Haange, R.*
Nuclear Fusion, 42(3), p.243 - 246, 2002/03
Times Cited Count：3 Percentile：10.54(Physics, Fluids & Plasmas)no abstracts in English
Kakudate, Satoshi; Oka, Kiyoshi; Yoshimi, Takashi*; Taguchi, Ko*; Nakahira, Masataka; Takeda, Nobukazu; Shibanuma, Kiyoshi; Obara, Kenjiro; Tada, Eisuke; Matsumoto, Yasuhiro*; et al.
Fusion Engineering and Design, 51-52(1-4), p.993 - 999, 2000/11
Times Cited Count：9 Percentile：53.47(Nuclear Science & Technology)no abstracts in English
Yoshida, Hiroshi; O.Kveton*; J.Koonce*; D.Holland*; Haange, R.*
Fusion Engineering and Design, 39-40, p.875 - 882, 1998/00
Times Cited Count：26 Percentile：86.20(Nuclear Science & Technology)no abstracts in English
Obara, Kenjiro; ; Kakudate, Satoshi; Oka, Kiyoshi; Nakahira, Masataka; Morita, Yosuke; ; ; Takeda, Nobukazu; Takahashi, Hiroyuki*; et al.
Fusion Engineering and Design, 42, p.501 - 509, 1998/00
Times Cited Count：3 Percentile：31.46(Nuclear Science & Technology)no abstracts in English
Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; ; Tada, Eisuke; ; Shibanuma, Kiyoshi; Haange, R.*; A.Tesini*
Fusion Technology 1996, 0, p.1649 - 1652, 1997/00
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
Penzhorn, R.-D.*; Abdallah, J.*; Haange, R.*; Hircq, B.*; Meikle, A.*; Naruse, Yuji
Fusion Engineering and Design, 16, p.141 - 157, 1991/12
Times Cited Count：11 Percentile：74.01(Nuclear Science & Technology)no abstracts in English
