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Journal Articles

Manufacturability and strength assessment of modified 9Cr-1Mo steel products for Japan sodium cooled fast reactor components, 2; Long thin-walled tubes with small diameter

Wakai, Takashi; Onizawa, Takashi; Obara, Satoshi; Nakashima, Takashi*; Yokoyama, Tetsuo*; Iseda, Atsuro*; Ogumo, Shinya*; Futagami, Satoshi*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2), p.171 - 181, 2011/07

To enhance the economic competitiveness, high-Cr ferritic steels are adopted as the structural materials for JSFR, because the steels have both excellent high temperature strength and thermal properties. Among the high-Cr ferritic steels, modified 9Cr-1Mo steel (compatible to ASTM A213 T91) is a candidate of the structural material for the demonstration facility of JSFR, because the steel has superior microstructure stability at elevated temperature for long time. As for the steam generator tubes, to enhance the safety, straight double-walled tubes will be employed. In this study, the following technical issues were investigated; (1) Industrial manufacturability of thin-walled small bore tubes made of modified 9Cr-1Mo steel, (2) performance demonstration of the thin-walled small bore tubes, (3) industrial manufacturability of double-walled tubes using the thin-walled small bore tubes and (4) extraction of technical problems to manufacture the double-walled tubes for the JSFR steam generator. As a result, thin-walled small bore tubes made of modified 9Cr-1Mo steel were successfully manufactured by using the existing industrial facilities, up to 17m in length. The mechanical properties of the tubes satisfy the requirements from plant designing, as well as those from the material strength standards. Further, double walled tubes were also manufactured, up to 15m in length. The surface conditions of the tubes and the contact pressure between inner and outer tubes should be optimized.

Journal Articles

Direct Extraction of Uranium and Plutonium from Oxide Fuel using TBP-HNO$$_{3}$$Complex for Super-DIREX Process

Kamiya, Masayoshi; Miura, Sachiko; Nomura, Kazunori; Koyama, Tomozo; Ogumo, Shinya*; Mori, Yukihide*; Enokida, Yoichi*

CD-ROM, P1-35, 4P., 4 Pages, 2004/00

Super-DIREX is a new reprocessing method which has high economical efficiency. Experimental study of this process was started on the direct extraction of U and Pu from irradiated MOX fuel by the supercritical carbon dioxide (SFCO$$_{2}$$) containing TBP-HNO$$_{3}$$ complex. This report describes direct extraction of U and Pu with TBP-HNO3 complex at atmospheric pressure, as the first test for irradiated fuel, in order to investigate the applicability of SFCO$$_{2}$$ containing TBP-HNO$$_{3}$$ complex. In this test, dependency on dissolution temperature, Pu content, fuel/ TBP-HNO$$_{3}$$ complex ratio and effect of voloxidation were investigated. From these results, TBP-HNO$$_{3}$$ complex was found to be effective in the respect of the recovery of U and Pu. The number of the process step in dissolution and co-extraction is small, and amount of waste can be reduced. It is applicable to the direct extraction in Super-DIREX.

Journal Articles

Extraction of Uranium and Plutonium from Irradiated Fuel in Super-DIREX Reprocessing Method

Miura, Sachiko; Kamiya, Masayoshi; Nomura, Kazunori; Miyachi, Shigehiko; Koyama, Tomozo; Ogumo, Shinya*; Shimada, Takashi*

Abstracts P.30, 30 Pages, 2003/00

None

Oral presentation

Design study of double wall straight tube steam generator, 2; Study on safety scenario

Ogumo, Shinya*; Tsujita, Yoshihiro*; Ando, Masato; Hori, Toru*; Hayafune, Hiroki

no journal, , 

Methodology of Na/water reaction avoidance was studied by mechanically bonded double wall tubes and the inspection of both inner and outer tubes during plant periodical inspections term.

Oral presentation

Conceptual design study and related R&Ds toward the demonstration reactor of JSFR, 3; Development of main structures made of high chrome steel for JSFR steam generator

Futagami, Satoshi; Hayafune, Hiroki; Enuma, Yasuhiro*; Ogumo, Shinya*; Hirayama, Tomoyuki*; Murakami, Hisatomo*

no journal, , 

no abstracts in English

Oral presentation

Development of advanced component toward the demonstration reactor of JSFR

Shimazaki, Masanori; Hayafune, Hiroki; Futagami, Satoshi; Enuma, Yasuhiro*; Kawamura, Masaya*; Ogumo, Shinya*

no journal, , 

no abstracts in English

Oral presentation

Development of the JSFR main components, 3; Productivity of the transfer tubes for steam generator

Kawamura, Masaya*; Ushiki, Hiroshi*; Enuma, Yasuhiro; Futagami, Satoshi; Ogumo, Shinya*; Ichihara, Takashi*; Nakashima, Takashi*

no journal, , 

no abstracts in English

Oral presentation

A Study on the straight double-walled tube steam generator design against sodium-water reaction in DECs

Kanda, Hironori; Enuma, Yasuhiro; Futagami, Satoshi; Kawamura, Masaya*; Ushiki, Hiroshi*; Ogumo, Shinya*; Ichihara, Takashi*; Nakashima, Takashi*

no journal, , 

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