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Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*
Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02
Times Cited Count:13 Percentile:64.88(Nuclear Science & Technology)no abstracts in English
Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Denki Gakkai Rombunshi, A, 125(11), p.943 - 946, 2005/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Enoeda, Mikio
Koon Gakkai-Shi, 30(5), p.256 - 262, 2004/09
Fabrication technologies for ITER in-vessel components, especially the shielding blanket with the separable first wall panel has been developed. Hot Isostatic Pressing (HIP) has been applied to the bonding of Cu-alloy/stainless steel and beryllium/Cu-alloy. First wall mock-ups fabricated by using HIP were tested under high heat fluxes and showed sufficient heat removal and thermal fatigue performance. Water jet and electrical discharge machining have been applied to manufacture slots into the first wall panel and the shield block. With these technologies, a first wall panel prototype and a shielding block 1/2 mock-up were successfully fabricated.
Kosaku, Yasuo; Kuroda, Toshimasa*; Hatano, Toshihisa; Enoeda, Mikio; Miki, Nobuharu*; Akiba, Masato
JAERI-Tech 2002-078, 58 Pages, 2002/10
Shielding blanket for ITER-FEAT applies the unique first wall structure which is separable from the shield block for the purpose of radio-active waste reduction in the maintenance work and cost reduction in fabrication process. Also, it is required to have various types of slots in both of the first wall and the shield block, to reduce the eddy current for reduction of electro-magnetic force in disruption events. This report summarizes the achievement of such R&Ds as, slit grooving techniques for Be/DSCu/SS first wall panel and SS shield block, demonstration of Be armor joining to the real scal first wall panel, and demonstration of full scale first wall panel.
Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Akiba, Masato
JAERI-Tech 2002-063, 98 Pages, 2002/07
no abstracts in English
Furuya, Kazuyuki; Sato, Satoshi; Hatano, Toshihisa; ; Kitamura, Kazunori*; Miura, H.*; ; Kuroda, Toshimasa*; Takatsu, Hideyuki
JAERI-Tech 97-022, 113 Pages, 1997/05
no abstracts in English
; Seki, Yasushi; Sato, Satoshi;
Purazuma, Kaku Yugo Gakkai-Shi, 71(10), p.987 - 1001, 1995/10
no abstracts in English
Furuya, Kazuyuki; Hashimoto, T.*; Sato, Satoshi; Kuroda, Toshimasa*; ; Kurasawa, Toshimasa; ; Takatsu, Hideyuki
JAERI-Tech 95-045, 53 Pages, 1995/09
no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Kurasawa, Toshimasa; Hashimoto, T.*; Koizumi, Koichi; ; ; ; Tada, Eisuke; Nakahira, Masataka; et al.
JAERI-Tech 95-019, 129 Pages, 1995/03
no abstracts in English
S.Zimin*; Sato, Satoshi; Hashimoto, T.*; Takatsu, Hideyuki
JAERI-Tech 94-026, 13 Pages, 1994/11
no abstracts in English
; Tone, Tatsuzo; ; Iida, Hiromasa; ;
Journal of Nuclear Science and Technology, 19(6), p.491 - 503, 1982/00
no abstracts in English
JAERI-M 8711, 117 Pages, 1980/02
no abstracts in English
; ; ; Furukawa, Kazuo
Journal of Nuclear Science and Technology, 15(1), p.76 - 78, 1978/01
Times Cited Count:1no abstracts in English