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Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo
Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01
Times Cited Count：10 Percentile：57.01(Nuclear Science & Technology)no abstracts in English
Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*
Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02
Times Cited Count：14 Percentile：64.72(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.
Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo
Fusion Science and Technology, 48(1), p.650 - 653, 2005/07
Times Cited Count：7 Percentile：44.05(Nuclear Science & Technology)no abstracts in English
Verzilov, Y. M.; Ochiai, Kentaro; Klix, A.; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo
Journal of Nuclear Materials, 329-333(Part2), p.1337 - 1341, 2004/08
Times Cited Count：4 Percentile：28.79(Materials Science, Multidisciplinary)no abstracts in English
Verzilov, Y. M.; Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo
JAERI-Research 2004-005, 30 Pages, 2004/03
JAERI-Research-2004-005.pdf:1.93MB
no abstracts in English
Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Sato, Shinichi*; Osaki, Toshio*; Miki, Nobuharu*; Akiba, Masato
JAERI-Tech 2003-058, 69 Pages, 2003/06
JAERI-Tech-2003-058.pdf:5.86MB
The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket.
Research Committee for Fusion Reactor; Research Committee for Fusion Materials
JAERI-Review 2003-015, 123 Pages, 2003/05
JAERI-Review-2003-015.pdf:24.89MB
no abstracts in English
Research Committee for Fusion Reactor; Research Committee for Fusion Materials
JAERI-Review 2002-008, 79 Pages, 2002/03
JAERI-Review-2002-008.pdf:9.92MB
Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi
Journal of Nuclear Science and Technology, 37(Suppl.1), p.423 - 426, 2000/03
no abstracts in English
Miura, H.*; Sato, Satoshi; Enoeda, Mikio; Kuroda, Toshimasa*; Takatsu, Hideyuki; Kawamura, Yoshinori; Tanaka, Satoru*
JAERI-Tech 97-051, 51 Pages, 1997/10
no abstracts in English
Miura, H.*; ; ; Takatsu, Hideyuki; Kuroda, Toshimasa*; Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Kurasawa, Toshimasa; ; et al.
Fusion Technology 1996, 0, p.1339 - 1342, 1997/00
no abstracts in English
Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Kosako, Kazuaki*; Nakamura, Tomoo; Maekawa, Hiroshi; M.Z.Youssef*; A.Kumar*; M.A.Abdou*; et al.
JAERI-M 94-015, 193 Pages, 1994/02
no abstracts in English
Oyama, Yukio
NCC Nyusu, 0(18), p.17 - 23, 1994/00
no abstracts in English
Oyama, Yukio; Maekawa, Hiroshi;
Nihon Genshiryoku Gakkai-Shi, 36(7), p.612 - 618, 1994/00
no abstracts in English
Nakagawa, Masayuki; Kosako, Kazuaki*; Mori, Takamasa; Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Yamaguchi, Seiya*; Tsuda, Koichi*; Maekawa, Hiroshi; ; et al.
JAERI-M 92-183, 106 Pages, 1992/12
no abstracts in English
Mori, Seiji*; ; Seki, Yasushi; Seki, Masahiro
FAPIG, 0(124), p.2 - 11, 1990/03
no abstracts in English
; Iida, Hiromasa;
JAERI-M 82-025, 23 Pages, 1982/03
no abstracts in English
