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Journal Articles

Neutronics design of the low aspect ratio tokamak reactor, VECTOR

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:29.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutron shielding and blanket neutronics study on low aspect ratio tokamak reactor

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.

Journal Articles

Development of fabrication technology of ITER shielding blanket

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.

JAEA Reports

Fabrication of the full scale separable first wall of ITER shielding blanket

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.

JAEA Reports

Fabrication of prototype mockups of ITER shielding blanket with separable first wall

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

JAEA Reports

Design of ITER shielding blanket

Furuya, Kazuyuki; Sato, Satoshi; Hatano, Toshihisa; *; Kitamura, Kazunori*; Miura, H.*; *; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 97-022, 113 Pages, 1997/05

JAERI-Tech-97-022.pdf:3.42MB

no abstracts in English

Journal Articles

Nuclear design for fusion reactors

*; Seki, Yasushi; Sato, Satoshi; *

Purazuma, Kaku Yugo Gakkai-Shi, 71(10), p.987 - 1001, 1995/10

no abstracts in English

JAEA Reports

Transient thermal and stress analyses of the ITER shielding blanket/first wall under off-normal conditions

Furuya, Kazuyuki; Hashimoto, T.*; Sato, Satoshi; Kuroda, Toshimasa*; *; Kurasawa, Toshimasa; *; Takatsu, Hideyuki

JAERI-Tech 95-045, 53 Pages, 1995/09

JAERI-Tech-95-045.pdf:3.13MB

no abstracts in English

JAEA Reports

Conceptual design of ITER shielding blanket

Sato, Satoshi; Takatsu, Hideyuki; Kurasawa, Toshimasa; Hashimoto, T.*; Koizumi, Koichi; *; *; *; Tada, Eisuke; Nakahira, Masataka; et al.

JAERI-Tech 95-019, 129 Pages, 1995/03

JAERI-Tech-95-019.pdf:3.27MB

no abstracts in English

JAEA Reports

Peaking factors of nuclear heating due to void ducts in the 80% SS-20% H$$_{2}$$O shielding blanket of fusion experimental reactors

S.Zimin*; Sato, Satoshi; Hashimoto, T.*; Takatsu, Hideyuki

JAERI-Tech 94-026, 13 Pages, 1994/11

JAERI-Tech-94-026.pdf:0.32MB

no abstracts in English

Journal Articles

Design study of swimming pool type tokamak reactor; SPTR

; Tone, Tatsuzo; ; ; *; *

Journal of Nuclear Science and Technology, 19(6), p.491 - 503, 1982/00

no abstracts in English

JAEA Reports

IAEA INTOR Workshop Report, Groups 2,5,7,9,10 and 15

JAERI-M 8711, 117 Pages, 1980/02

JAERI-M-8711.pdf:2.92MB

no abstracts in English

Journal Articles

Nuclear characteristics of molten-salt-cooled D-D fusion reactor blankets

*; *; *; Furukawa, Kazuo

Journal of Nuclear Science and Technology, 15(1), p.76 - 78, 1978/01

 Times Cited Count:1

no abstracts in English

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