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Suzuki, Satoshi; Ezato, Koichiro; Hirose, Takanori; Sato, Kazuyoshi; Yoshida, Hajime; Enoeda, Mikio; Akiba, Masato
Fusion Engineering and Design, 81(1-7), p.93 - 103, 2006/02
Times Cited Count：12 Percentile：63.1(Nuclear Science & Technology)This paper presents an R&D activity on the plasma facing components (PFCs), such as first wall and divertor, for the fusion power plant. The PFCs of the power plant will be subjected to heavy neutron irradiation and high heat/particle flux from plasma during the continuous operation. In the present design of the PFCs, the candidate structural material is a reduced activation ferritic-martensitic steel, F82H, from the viewpoints of low activation and high robustness against neutron irradiation, and the candidate armor material is tungsten from the low sputtering yield and low tritium retention points of view. To realize the PFCs using such materials, JAERI has bee extensively conducting R&Ds on; (1) high performance cooling tube, (2) tungsten armor materials, (3) selection of a bonding technique for F82H and tungsten materials and (4) evaluation of structural integrity. Recent achievements on these R&Ds are presented.
Furuya, Kazuyuki
JAERI-Research 2004-013, 165 Pages, 2004/09
JAERI-Research-2004-013.pdf:53.73MB
no abstracts in English
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.
Suzuki, Satoshi
Koon Gakkai-Shi, 30(5), p.243 - 247, 2004/09
Selection and the development of plasma facing materials for fusion devices, mainly ITER, are presented. For the divertor, CFC (Carbon fiber reinforced carbon composite) materials are utilized as plasma facing materials in the lower part of vertical targets in ITER. Since the design maximum heat flux to the vertical targets is 20 MW/m
, CFC materials, which have higher thermal conductivity than pure copper, are preferable from a heat removal point of view. On the other hand, a plasma facing material of a dome and a liner is tungsten because tungsten has low sputtering yield and has relatively high thermal conductivity among metals. First wall covers 80% of the plasma facing area of ITER. The plasma facing material of the first wall should have good compatibility with plasma. Therefore, beryllium is utilized as a plasma facing material from the low contamination and the minimization of the oxygen impurity to the plasma points of view.
Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09
no abstracts in English
Masaki, Kei; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Goto, Yoshitaka*; Tobita, Kenji; Miyo, Yasuhiko; Kaminaga, Atsushi; Kodama, Kozo; Arai, Takashi; Miya, Naoyuki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.130 - 139, 2003/06
no abstracts in English
Kosaku, Yasuo; Kuroda, Toshimasa*; Hatano, Toshihisa; Enoeda, Mikio; Miki, Nobuharu*; Akiba, Masato
JAERI-Tech 2002-078, 58 Pages, 2002/10
JAERI-Tech-2002-078.pdf:19.38MB
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.
Hatano, Toshihisa; Enoeda, Mikio; Kuroda, Toshimasa*; Akiba, Masato
JAERI-Tech 2002-075, 59 Pages, 2002/10
JAERI-Tech-2002-075.pdf:17.38MB
no abstracts in English
Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Akiba, Masato
JAERI-Tech 2002-063, 98 Pages, 2002/07
JAERI-Tech-2002-063.pdf:11.16MB
no abstracts in English
ITER Physics Expert Group on Disruptions, Plasma Control, and MHD; ITER Physics Expert Group on Energetic Particles, Heating and Current Drive; ITER Physics Expert Group on Diagnostics
Nuclear Fusion, 39(12), p.2577 - 2625, 1999/00
no abstracts in English
*; Abe, Mitsushi*; Tadokoro, Takahiro*; Miura, Yukitoshi; Suzuki, Norio; Sato, Masayasu; Sengoku, Seio
Purazuma, Kaku Yugo Gakkai-Shi, 74(3), p.274 - 283, 1998/03
no abstracts in English
Sato, Satoshi; Hatano, Toshihisa; Furuya, Kazuyuki; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki
JAERI-Research 97-092, 80 Pages, 1998/01
JAERI-Research-97-092.pdf:5.11MB
no abstracts in English
Hatano, Toshihisa; ; ; *; *; Kitamura, Kazunori*; Kuroda, Toshimasa*; Akiba, Masato; Takatsu, Hideyuki
Fusion Engineering and Design, 39-40, p.363 - 370, 1998/00
Times Cited Count：20 Percentile：81.49(Nuclear Science & Technology)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
C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60Jimbo, Ryutaro*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; *
Journal of the Ceramic Society of Japan, International Edition, 105, p.1179 - 1187, 1997/00
no abstracts in English
*; Komatsuzaki, Manabu*; Nishio, Satoshi; Koizumi, Koichi; Takatsu, Hideyuki
JAERI-Tech 96-031, 16 Pages, 1996/07
no abstracts in English
Sato, Satoshi; Furuya, Kazuyuki; Kuroda, Toshimasa*; Kurasawa, Toshimasa; *; Hatano, Toshihisa; Takatsu, Hideyuki; Osaki, Toshio*
16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.202 - 205, 1996/00
no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Hashimoto, T.*; Kurasawa, Toshimasa; Furuya, Kazuyuki; *; Osaki, Toshio*; Kuroda, Toshimasa*
Journal of Nuclear Materials, 233-237(PT.B), p.940 - 944, 1996/00
Times Cited Count：34 Percentile：92(Materials Science, Multidisciplinary)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
Koizumi, Koichi; *; Nakahira, Masataka; Takatsu, Hideyuki; Tada, Eisuke; Seki, Masahiro; Tsunematsu, Toshihide
Fusion Engineering and Design, 27, p.388 - 398, 1995/00
no abstracts in English
