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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

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

7 (Records 1-7 displayed on this page)
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