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JAEA Reports

Nuclear, thermo-mechanical and tritium release analysis of ITER breeding blanket

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.

Journal Articles

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

 Times Cited Count:11 Percentile:60.05(Nuclear Science & Technology)

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$$^{2}$$, 13000 cycles. Full-scale separate FW panels (dimensions: 0.9$$times$$0.25$$times$$0.07 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.

Journal Articles

Estimation of mechanical characteristics of actual size rubber bearings with scale models

Yabana, Shuichi*; Matsuda, Akihiro*; Nakahira, Masataka; Osaki, Toshio*

Nihon Kenchiku Gakkai 2002-Nendo Taikai Koen Kogaishu, P. 495, 2002/08

no abstracts in English

JAEA Reports

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

Journal Articles

Memories of Garching

Osaki, Toshio*

FAPIG, (159), p.3 - 9, 2001/11

no abstracts in English

Journal Articles

${it In-situ}$ tritium recovery experiments of blanket in-pile mockup with Li$$_{2}$$TiO$$_{3}$$ 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

 Times Cited Count:22 Percentile:82.72(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

ITER breeding blanket module design & analysis

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

JAERI-Tech 98-051, 71 Pages, 1998/11

JAERI-Tech-98-051.pdf:2.74MB

no abstracts in English

Journal Articles

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

Journal Articles

Fabrication of a small-scaled first wall mock-up with beryllium armor HIP bonded to DSCU/SS structure

Hatano, Toshihisa; Kuroda, Toshimasa*; Iwadachi, Takaharu*; Osaki, Toshio*; Enoeda, Mikio; Takatsu, Hideyuki

Fusion Technology 1998, 1, p.97 - 100, 1998/00

no abstracts in English

Journal Articles

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

Journal Articles

Design development of breeding blanket based on pebble bed concept for fusion experimental reactor

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

Journal Articles

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

Journal Articles

Mechanical properties of HIP bonded joints of austenitic stainless steel and Cu-alloy for fusion experimental reactor blanket

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:33 Percentile:92.33(Materials Science, Multidisciplinary)

no abstracts in English

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