Progress on design and R&D of ITER FW/blanket

Ioki, Kimihiro*; Akiba, Masato; Cardella, A.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Lorenzetto, P.*; Miki, Nobuharu*; Osaki, Toshio*; Rozov, V.*; et al.

Fusion Engineering and Design, 61-62, p.399 - 405, 2002/11

https://doi.org/10.1016/S0920-3796(02)00109-6

We report progress on the ITER-FEAT Blanket design and R&D during 2001-2002. Four major sub-components (FW, shield body, flexible support and electrical connection) have been highlighted. Regarding the FW, design on a separate FW panel concept has progressed, and heat load tests on a small-scale mock-up have been successfully performed with 0.7 MW/m, 13000 cycles. Full-scale separate FW panels (dimensions: 0.90.250.07 m) have been fabricated by HIPing and brazing. Regarding the shield body, a radial flow cooling design has been developed, and full-scale partial mock-ups have been fabricated by using water-jet cutting. A separate FW panel was assembled with one the shield body mock-ups. Regarding the flexible support, mill-annealed Ti (easier fabricability) alloy has been selected, and the remote assembly has been considered in the design. In mechanical tests, the requires buckling strength and mechanical fatigue characteristics have been confirmed. Regarding the electrical connection, one-body structure design without welding joints has been developed. Mechanical fatigue tests in the 3 directions, have been carried out, and thermal fatigue tests and electrical tests in a solenoidal magnetic field have been performed. Feasibility of the design has been confirmed. Through progress on design and R&D of the blanket, cost reduction has been achieved, and feasibility of design and fabricability of the components have been confirmed.

Development of fabrication technologies for ITER in-vessel components

Kuroda, Toshimasa*; Sato, Kazuyoshi; Akiba, Masato; Ezato, Koichiro; Enoeda, Mikio; Osaki, Toshio*; Kosaku, Yasuo; Sato, Satoshi; Sato, Shinichi*; Suzuki, Satoshi*; et al.

JAERI-Tech 2002-044, 25 Pages, 2002/03

JAERI-Tech-2002-044.pdf:2.68MB

no abstracts in English

tritium recovery experiments of blanket in-pile mockup with LiTiO pebble bed in Japan

Tsuchiya, Kunihiko; Nakamichi, Masaru; Nagao, Yoshiharu; Enoeda, Mikio; Osaki, Toshio*; Tanaka, Satoru*; Kawamura, Hiroshi

Journal of Nuclear Science and Technology, 38(11), p.996 - 1003, 2001/11

https://doi.org/10.3327/jnst.38.996

no abstracts in English

Fabrication of an ITER shielding blanket prototype

Sato, Satoshi; Takatsu, Hideyuki; Enoeda, Mikio; Furuya, Kazuyuki; Hatano, Toshihisa; Kuroda, Toshimasa*; Osaki, Toshio*; *; Sato, Shinichi*; Ohara, Yoshihiro

Fusion Technology, 34(3), p.892 - 897, 1998/11

no abstracts in English

Fabrication of small-scaled shielding blanket module and first wall panel for international thermonuclear experimental reactor

Furuya, Kazuyuki; Sato, Satoshi; Miura, H.*; Kuroda, Toshimasa*; Kurasawa, Toshimasa; *; Hatano, Toshihisa; Takatsu, Hideyuki; Osaki, Toshio*; Sato, Shinichi*; et al.

Fusion Technology 1996, 0, p.1343 - 1346, 1997/00

no abstracts in English

Fabrication of HIPped first wall panel for fusion experimental reactor and preliminary analyses for its thermo-mechanical test

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