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Journal Articles

ITER project and fusion technology

Takatsu, Hideyuki

Nuclear Fusion, 51(9), p.094002_1 - 094002_16, 2011/09

 Times Cited Count:5 Percentile:70.5(Physics, Fluids & Plasmas)

This is a summary paper on the three sessions on ITER (ITR), Fusion Technology (FTP) and Safety, Environment and Economic Aspect of Fusion Energy (SEE) presented at the 23rd IAEA Fusion Energy Conference in October, 2010, in Daejon, South Korea. Highlights of the three sessions are summarized with a minimum set of background information.

Journal Articles

ITER project; Status of procurement activities in domestic agency of Japan and application of HIP technology

Takatsu, Hideyuki; Enoeda, Mikio; Suzuki, Satoshi; Hirose, Takanori; Koizumi, Norikiyo; Takahashi, Koji

Proceedings of International Conference on Hot Isostatic Pressing (HIP '11), p.35 - 40, 2011/04

ITER is a mega-science fusion project, under an international collaboration of seven Members, to construct, operate, exploit and decommission a tokamak-type experimental reactor at Cadarache site with a mission to demonstrate the scientific and technological feasibility. The ITER Project started technical activities in 2007 and is now in a serious construction phase. Domestic Agencies of the seven member countries are in the process of manufacturing long lead-time components. Some of the ITER components apply HIP technology in manufacturing processes in view of a number of potential advantages. In this paper, examples and status of application of HIP technology by the Domestic Agency of Japan are overviewed.

Journal Articles

Design and trial fabrication of a dismantling apparatus for irradiation capsules of solid tritium breeder materials

Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Takatsu, Hideyuki; Nakamura, Mutsumi*; Noguchi, Tsuneyuki*

Journal of Nuclear Materials, 386-388, p.1083 - 1086, 2009/04

 Times Cited Count:0 Percentile:100(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Fusion materials development program in the Broader Approach activities

Nishitani, Takeo; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Nozawa, Takashi; Hayashi, Kimio; Yamanishi, Toshihiko; Tsuchiya, Kunihiko; M$"o$slang, A.*; Baluc, N.*; Pizzuto, A.*; et al.

Journal of Nuclear Materials, 386-388, p.405 - 410, 2009/04

 Times Cited Count:29 Percentile:8.52(Materials Science, Multidisciplinary)

The establishment of the breeding blanket technology is one of the most important engineering issues on the DEMO development. For the DEMO blanket, developments of the structural materials and functional materials such as tritium breeder and neutron multiplier. Which should be used under the savior circumstance such as high neutron fluence, high temperature and strong magnetic field, are urgent issues. In the Broader Approach activities initiated by EU and Japan, developments of reduced activation ferritic martensitic steels as a DEMO blanket structural material, SiC/SiC composites, advanced tritium breeders and neutron multiplier for DEMO blankets, are planed as common interest issues of EU and Japan. This paper describes the overview of the development program.

JAEA Reports

Investigation and design of the dismantling process of irradiation capsules containing tritium, 2; Detailed design and trial fabrication of capsule dismantling apparatus and investigation of glove box facility

Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Katsuyama, Kozo; Iwamatsu, Shigemi; Hasegawa, Teiji; Kodaka, Hideo; Takatsu, Hideyuki; et al.

JAEA-Technology 2009-007, 168 Pages, 2009/03

JAEA-Technology-2009-007.pdf:31.88MB

In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of lithium titanate (Li$$_{2}$$TiO$$_{3}$$), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes (1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and (2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, datailed specifications and the installation methods were examined, based on results of a conceptual design and basic design. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility.

Journal Articles

Japanese perspective of fusion nuclear technology from ITER to DEMO

Tanaka, Satoru*; Takatsu, Hideyuki

Fusion Engineering and Design, 83(7-9), p.865 - 869, 2008/12

 Times Cited Count:9 Percentile:43.19(Nuclear Science & Technology)

The world fusion community is now launching construction of ITER. In parallel with the ITER Program, Broader Approach activities also started this year by the collaboration of Japan and EURATOM. The Atomic Energy Commission of Japan reviewed the on-going Third Phase Basic Program of Fusion Research and Development, and then issued the Report in November 2005. This report presented a roadmap toward the DEMO and beyond and identified research and development items on fusion nuclear technology indispensable for fusion energy utilization. In the present paper, Japanese view and policy on ITER and beyond will be summarized mainly from the viewpoints of fusion nuclear technology, and a minimum set of research and development items on fusion nuclear technology toward DEMO and essential for fusion energy utilization are overviewed.

JAEA Reports

Investigation and design of the dismantling process of irradiation capsules containing tritium, 1; Conceptual investigation and basic design

Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Kodaka, Hideo; Katsuyama, Kozo; Kitajima, Toshio; Takahashi, Kozo; Tsuchiya, Kunihiko; Nakamichi, Masaru; et al.

JAEA-Technology 2008-010, 68 Pages, 2008/03

JAEA-Technology-2008-010.pdf:11.31MB

In-pile functional tests of breeding blankets for fusion reactors have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in ITER. The present report describes a conceptual investigation and a basic design of the dismantling process for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA. In the present design, the irradiation capsule is cut by a band saw; the released tritium is recovered safely by a purge-gas system, and is consolidated into a radioactive waste form. Furthermore, adoption of the inner-box enclosing the dismantling apparatus has brought a prospect to be able to utilize an existing hot cell (beta-$$gamma$$ cell) equipped with usual wall material permeable to tritium, without extensive refurbishing of the cell. Thus, the present study has indicated the feasibility of the present dismantling process for the irradiated JMTR capsules containing tritium.

Journal Articles

Research and development of nuclear fusion

Ushigusa, Kenkichi; Seki, Masahiro; Ninomiya, Hiromasa; Norimatsu, Takayoshi*; Kamada, Yutaka; Mori, Masahiro; Okuno, Kiyoshi; Shibanuma, Kiyoshi; Inoue, Takashi; Sakamoto, Keishi; et al.

Genshiryoku Handobukku, p.906 - 1029, 2007/11

no abstracts in English

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

Journal Articles

Technology research and development issues and deployment plan toward fusion DEMO plant

Takatsu, Hideyuki; Konishi, Satoshi*

Purazuma, Kaku Yugo Gakkai-Shi, 81(11), p.837 - 902, 2005/11

Technology research and development issues, other than Breeding Blankets and Structural Materials, nesessary to be developed toward a fusion DEMO plant are introduced. Taking five critical technologies (Divertor, Superconducting Magnets, Tritium System, Heating and Current Drive system and Remote Maintenance System), target specifications and current status of technology research and development are outlined.

Journal Articles

Overview on materials R&D activities in Japan towards ITER construction and operation

Takatsu, Hideyuki; Sato, Kazuyoshi; Hamada, Kazuya; Nakahira, Masataka; Suzuki, Satoshi; Nakajima, Hideo; Kuroda, Toshimasa*; Nishitani, Takeo; Shikama, Tatsuo*; Shu, Wataru

Journal of Nuclear Materials, 329-333(1), p.178 - 182, 2004/08

 Times Cited Count:2 Percentile:80.44(Materials Science, Multidisciplinary)

This paper presents an overview on ITER-supporting materials research and development activities and major achievements in Japan during the period from the Co-ordinated Technical Activities to date. In view of the completed engineering design of ITER during the Engineering Design Activities period, research and development efforts since then have been focused: those for reduction of component fabrication cost; those in support of domestic preparations of a structural technical code for construction; those necessary for operation, and been extended to component-level testing rather than pure material testing. They cover materials Research and Development for in-vessel components, vacuum vessel, cryogenic steels of superconducting mgnet and diagnostics components. Major achievements in each research and development area are highlighted and their impact or implication to the design, construction and operation of ITER is presented.

JAEA Reports

Development of ITER shielding blanket prototype mockup by HIP bonding

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

JAERI-Tech 2000-042, 121 Pages, 2000/07

JAERI-Tech-2000-042.pdf:58.33MB

no abstracts in English

JAEA Reports

Heating facility for brlanket and performance test

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

JAERI-Tech 99-025, 45 Pages, 1999/03

JAERI-Tech-99-025.pdf:3.46MB

no abstracts in English

JAEA Reports

Fabrication and testing of small scale mock-ups of ITER shielding blanket

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

JAERI-Tech 98-058, 77 Pages, 1998/12

JAERI-Tech-98-058.pdf:6.08MB

no abstracts in English

JAEA Reports

Design & analysis of ITER shield blanket

*; Hatano, Toshihisa; *; *; Miura, H.*; Kuroda, Toshimasa*; Furuya, Kazuyuki; Sato, Satoshi; Enoeda, Mikio; Takatsu, Hideyuki; et al.

JAERI-Tech 98-055, 97 Pages, 1998/12

JAERI-Tech-98-055.pdf:3.16MB

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

Shielding analyses of the ITER NBI ports

Sato, Satoshi; Takatsu, Hideyuki; Seki, Yasushi; *; *; Iida, Hiromasa; Plenteda, R.*; Santoro, R. T.*; Valenza, D.*; Ohara, Yoshihiro; et al.

Fusion Technology, 34(3), p.1002 - 1007, 1998/11

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 and thermal cycle testing of a first wall mock-up for ITER baffle blanket module

Hatano, Toshihisa; ; *; Kuroda, Toshimasa*; ; Takatsu, Hideyuki; Akiba, Masato

Fusion Technology, 34, p.908 - 913, 1998/11

no abstracts in English

Journal Articles

Low cycle fatigue lifetime of HIP bonded Bi-metallic first wall structures of fusion reactors

Hatano, Toshihisa; Sato, Satoshi; Hashimoto, T.*; Kitamura, Kazunori*; Furuya, Kazuyuki; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki

Journal of Nuclear Science and Technology, 35(10), p.705 - 711, 1998/10

 Times Cited Count:1 Percentile:83.3(Nuclear Science & Technology)

no abstracts in English

115 (Records 1-20 displayed on this page)