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Journal Articles

Dismantlement of large fusion experimental device JT-60U

Ikeda, Yoshitaka; Okano, Fuminori; Sakasai, Akira; Hanada, Masaya; Akino, Noboru; Ichige, Hisashi; Kaminaga, Atsushi; Kiyono, Kimihiro; Kubo, Hirotaka; Kobayashi, Kazuhiro; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 13(4), p.167 - 178, 2014/12

The JT-60U torus was disassembled so as to newly install the superconducting tokamak JT-60SA torus. The JT-60U used the deuterium for 18 years, so the disassembly project of the JT-60U was the first disassembly experience of a fusion device with radioactivation in Japan. All disassembly components were stored with recording the data such as dose rate, weight and kind of material, so as to apply the clearance level regulation in future. The lessons learned from the disassembly project indicated that the cutting technologies and storage management of disassembly components were the key factors to conduct the disassembly project in an efficient way. After completing the disassembly project, efforts have been made to analyze the data for characterizing disassembly activities, so as to contribute the estimation of manpower needs and the radioactivation of the disassembly components on other fusion devices.

Journal Articles

Safe disassembly and storage of radioactive components of JT-60U torus

Ikeda, Yoshitaka; Okano, Fuminori; Hanada, Masaya; Sakasai, Akira; Kubo, Hirotaka; Akino, Noboru; Chiba, Shinichi; Ichige, Hisashi; Kaminaga, Atsushi; Kiyono, Kimihiro; et al.

Fusion Engineering and Design, 89(9-10), p.2018 - 2023, 2014/10

 Times Cited Count:2 Percentile:19.81(Nuclear Science & Technology)

Disassembly of the JT-60U torus was started in 2009 after 18-years D$$_{2}$$ operations, and was completed in October 2012. The JT-60U torus was featured by the complicated and welded structure against the strong electromagnetic force, and by the radioactivation due to D-D reactions. Since this work is the first experience of disassembling a large radioactive fusion device in Japan, careful disassembly activities have been made. About 13,000 components cut into pieces with measuring the dose rates were removed from the torus hall and stored safely in storage facilities by using a total wokers of 41,000 person-days during 3 years. The total weight of the disassembly components reached up to 5,400 tons. Most of the disassembly components will be treated as non-radioactive ones after the clearance verification under the Japanese regulation in future. The assembly of JT-60SA has started in January 2013 after this disassembly of JT-60U torus.

Journal Articles

In-service inspection and repair program for commercialized sodium-cooled fast reactor

Nishiyama, Noboru; Kotake, Shoji*; Uzawa, Masayuki*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 9 Pages, 2012/00

Japan Sodium-cooled Fast Reactor (JSFR) adopts a compact design to reduce construction cost as a commercialized reactor. A commercialized fast reactor is also expected to be excellent in operation and maintenance for high availability. From the study for JSFR, in-service inspection and repair program necessary for JSFR has been developed. Major component design has been improved considering ISI accommodation, and the required ISI devices have been specified according to the proposed ISI program. To increase maintainability of JSFR, such approaches are employed at the conceptual design stage.

Journal Articles

Conceptual design study for the demonstration reactor of JSFR, 6; Fuel handling system design

Chikazawa, Yoshitaka; Kato, Atsushi; Obata, Hiroyuki*; Nishiyama, Noboru; Uzawa, Masayuki*; Tozawa, Katsuhiro*; Chishiro, Ryo*

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10

A preliminary design of the JSFR fuel handling system has been proposed. FaCT phase I results of key technology evaluations on preliminary safety assessment, a pantograph fuel handling machine, a sodium pot with two core component positions, dry spent fuel cleaning and minor actinide-bearing fresh fuel shipping cask are provided.

Journal Articles

A Study on 3-GeV proton beam transport line for JSNS

Meigo, Shinichiro; Harada, Masahide; Konno, Chikara; Ikeda, Yujiro; Watanabe, Noboru; Sakamoto, Shinichi*; Muto, Suguru*; Miyake, Yasuhiro*; Nishiyama, Kusuo*; Shimomura, Koichiro*; et al.

JAERI-Conf 2001-002, p.314 - 324, 2001/03

no abstracts in English

Oral presentation

Study of disassembly on JT-60U tokamak device

Okano, Fuminori; Miyo, Yasuhiko; Nishiyama, Tomokazu; Sato, Yoji; Sasaki, Noboru*; Honda, Masao*; Sakasai, Akira; Sato, Masayasu

no journal, , 

no abstracts in English

Oral presentation

Study of disassembly on JT-60U tokamak device

Okano, Fuminori; Miyo, Yasuhiko; Nishiyama, Tomokazu; Sato, Yoji; Sasaki, Noboru*; Oikawa, Akira; Sakai, Toshiya; Sato, Masayasu

no journal, , 

no abstracts in English

Oral presentation

Study of disassembly and cutting technology for JT-60U tokamak device

Nishiyama, Tomokazu; Okano, Fuminori; Miyo, Yasuhiko; Sasaki, Noboru*; Meguro, Masashi*; Tajika, Masaharu*; Sato, Yoji; Sato, Masayasu

no journal, , 

no abstracts in English

Oral presentation

Development of fuel handling system in FaCT project, 6; Safety study on JSFR fuel handling system

Chikazawa, Yoshitaka; Kato, Atsushi; Uzawa, Masayuki*; Tozawa, Katsuhiro*; Chishiro, Ryo*; Obata, Hiroyuki*; Nishiyama, Noboru

no journal, , 

no abstracts in English

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