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Journal Articles

Welding technology on sector assembly of the JT-60SA vacuum vessel

Shibama, Yusuke; Okano, Fuminori; Yagyu, Junichi; Kaminaga, Atsushi; Miyo, Yasuhiko; Hayakawa, Atsuro*; Sagawa, Keiich*; Mochida, Tsutomu*; Morimoto, Tamotsu*; Hamada, Takashi*; et al.

Fusion Engineering and Design, 98-99, p.1614 - 1619, 2015/10

 Times Cited Count:4 Percentile:32.95(Nuclear Science & Technology)

The JT-60SA vacuum vessel (150 tons) is a double wall torus structure and the maximum major radius of 5.0 m and height of 6.6 m. The manufacturing design concept is that the vessel is split in the 10 toroidal sectors manufactured at factory, and assembled on-site; seven of the 40-degree sectors, two of the 30-degree beside final one, and the final of the 20-degree. The final sector is assembled with the VV thermal shield and toroidal field magnets into the 340-degree as prepared in one sector. Sectors are temporally fitted on-site and adjusted one over the other before the assembly. After measurement of the dimensions and the reference, these sectors are transferred onto the cryostat base. First, three 80-degree sectors are manufactured with mating each 40-degree sector by direct joint welding. The rest sectors including the final sector are jointed with splice plates. Welding manipulator and its guide rails are used for these welding. In this paper, the detail of the VV sectors assembly including the final sector is explained. Welding technologies to joint the two of 40-degree sectors are reported with the present manufacturing status and the welding trial on the vertical stub with the partial mock-up of the final sector are discussed with the assembly process.

JAEA Reports

Study on Thermal Electric Conversion System for Sodium cooled FBR; Investigation for development of thermoelectric materials and systematic technology

Suzuki, Ryosuke*; Tanabe, Kentaro*; kondo, koki*; Ono, Katsutoshi*; Toda, Shinichi; Kasagawa, Yusuke; Tamayama, Kiyoshi; Oketani, Kazuhiro*

JNC TY4400 2003-004, 214 Pages, 2003/08

JNC-TY4400-2003-004.pdf:19.93MB

Recently, it has been important to reuse discharged heat energy from present nuclear plants in the view of reduction of environmental burden and improvement of heat efficiency for plant. For practical use in future of sodium cooled FBRs, which are typical high temperature system, this issue must be given priority. The thermal electric conversion system has been applied to the limited uses such as space or military, however, that results show good merits for reliability, maintenance free, and so on. Recently, this technology has been reconsidered in the view of saving energy in general industry. In this study, we made an investigation for applicability of the thermal electric conversion system to sodium cooled FBR as a heat recovery techbnology. Exactly, We have carried out the fundamental research and development for thermoelectric materials and elements, development of modules, and sodium tests with those modules, and then, we acquired the fundamental knowledge to estimate the efficiencies of thermal electric conversion system or modules for a sodium cooled FBR.

JAEA Reports

Applicability of thermoelectric power generation system to Monju

Aizawa, Tatsuhiko*; Yamamoto, Shigeo*; Kim, S.*; Yang, J.*; Iwasako, Yasushi*; Toda, Shinichi; Kasagawa, Yusuke; Sakata, Hideaki; Oketani, Kazuhiro*

JNC TY4400 2003-003, 100 Pages, 2003/08

JNC-TY4400-2003-003.pdf:14.97MB

How to utilize the waste of heat is one of the most important issues for nuclear engineering. Its technological impact is significant in reduction of environmental burdens and minimization of CO2 emission through nuclear power generation with high efficiency. Research and development for thermoelectric power generation still weighs its importance on the search for high figure-of-merit materials; many engineering issues are still present to be solved toward promising solution to engineering issues are still present to be solved toward promising solution to engineering demand from market. Inthis study, new engineering ideas are proposed to make full use of heat waste via the prototype system for thermoelectric power generation. Sodium loop at the International Cooperation and Technology Development Center of Tsuruga Head Office in JNC was used as a heat source to demonstrate the effectiveness of the developed prototype system. The present research activities are categorized by the following elements.

Oral presentation

Completion of vacuum vessel sector manufacturing and subsequent torus assembly for the JT-60SA

Asano, Shiro*; Okuyama, Toshihisa*; Ejiri, Mitsuru*; Mizumaki, Shoichi*; Mochida, Tsutomu*; Hamada, Takashi*; Araki, Takao*; Hayakawa, Atsuro*; Sagawa, Keiich*; Kai, Toshiya*; et al.

no journal, , 

no abstracts in English

Oral presentation

Sector manufacturing and assembly of the JT-60SA vacuum vessel

Shibama, Yusuke; Okano, Fuminori; Yagyu, Junichi; Kaminaga, Atsushi; Miyo, Yasuhiko; Hayakawa, Atsuro*; Sagawa, Keiich*; Mochida, Tsutomu*; Morimoto, Tamotsu*; Hamada, Takashi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 15; Salt deposition on zeolite after the full-scale drying test

Sagawa, Yusuke*; Yamagishi, Isao; Terada, Atsuhiko; Uruga, Kazuyoshi*; Tsukada, Takeshi*

no journal, , 

no abstracts in English

Oral presentation

Cs retention property of geopolymer waste

Arisaka, Makoto; Kato, Tomoaki; Sagawa, Yusuke*; Cantarel, V.

no journal, , 

no abstracts in English

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