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Wakai, Eiichi; Watanabe, Kazuyoshi*; Ito, Yuzuru*; Suzuki, Akihiro*; Terai, Takayuki*; Yagi, Juro*; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; et al.
Plasma and Fusion Research (Internet), 11, p.2405112_1 - 2405112_4, 2016/11
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.
Fusion Science and Technology, 66(1), p.46 - 56, 2014/07
Times Cited Count：4 Percentile：29.67(Nuclear Science & Technology)Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Fukada, Satoshi*; Yagi, Juro*; Ida, Mizuho; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 88(12), p.691 - 705, 2012/12
no abstracts in English
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Kazuyuki; Ida, Mizuho; Watanabe, Kazuyoshi; Kanemura, Takuji; Wakai, Eiichi; Horiike, Hiroshi*; Yamaoka, Nobuo*; et al.
Nuclear Fusion, 51(12), p.123008_1 - 123008_12, 2011/12
Times Cited Count：39 Percentile：82.00(Physics, Fluids & Plasmas)The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Hiroo*; Ida, Mizuho; Watanabe, Kazuyoshi; Miyashita, Makoto*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Kanemura, Takuji; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10
The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.
Wakai, Eiichi; Kikuchi, Takayuki; Hirano, Michiko; Ida, Mizuho; Niitsuma, Shigeto; Kimura, Haruyuki; Nishitani, Takeo; Yamamoto, Michiyoshi; Matsumoto, Hiroshi; Sugimoto, Masayoshi; et al.
no journal, ,
no abstracts in English
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Ida, Mizuho; Watanabe, Kazuyoshi; Kim, B. J.; Fujishiro, Koji; Sugimoto, Masayoshi; Kimura, Haruyuki; Niitsuma, Shigeto
no journal, ,
no abstracts in English
Fujishiro, Koji; Ida, Mizuho; Tsuji, Yoshiyuki*; Wakai, Eiichi; Groeschel, F.*; Kondo, Hiroo; Kanemura, Takuji; Sugimoto, Masayoshi; Nishitani, Takeo
no journal, ,
no abstracts in English
Kiriyama, Koji; Shobu, Takahisa; Shibano, Junichi*; Fujishiro, Tomoyuki; Kaneko, Hiroshi; Miura, Setsuo*
no journal, ,
Fujishiro, Tomoyuki; Shobu, Takahisa; Terasawa, Michitaka*; Yamamoto, Atsushi*; Kiriyama, Koji*; Nakahigashi, Shigeo*; Hasegawa, Tadayuki*
no journal, ,
no abstracts in English
Fujishiro, Koji; Ida, Mizuho; Groeshel, F.*; Kondo, Hiroo; Wakai, Eiichi; Sugimoto, Masayoshi
no journal, ,
International Fusion Materials Irradiation Facility (IFMIF) is a high-intensity neutron source that simulates fusion neutron (14 MeV), and is being planned aiming at the development of fusion reactor materials. Since 2007, Engineering Varidation and Engineering Design Activities (EVEDA) has been promoted in cooperation with Japan and Europe. In the target assembly, the requirement onto each difficulties are exist (i.e. form a stable lithium jet: thickness 25 with 2 mm accuracy, nozzle exit velocity 20 m/s under high vacuum (10
Pa]) condition), and multi-focused countermeasures has been made. In this study, Flow Straightener which plays an important role for the stability of the lithium jet and which is designed and manufactured for EVEDA test facility, was evaluated under negative pressure environment using code FLUENT. The Flow Straightener has a shape conversion unit, a honeycomb and some porous plates. According the result of this analysis, it was found that the rectification properly of Flow Straightener is obtained as the function of the distance with the nozzle inlet and the most-downstream perforated plate, and was found that commutation state is obtained to adjust this length.
Fujishiro, Koji; Ida, Mizuho; Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Friedrich, G.*
no journal, ,
International Fusion Materials Irradiation Facility (IFMIF) is an activity to evaluate design of the facility of high-intensity neutron source at 14 MeV for nuclear fusion research and development to evaluate the fusion reactor materials. And Engineering Varidation and Engineering Design Activities (EVEDA) has been promoted under "Broader Approach (BA) Activities" with European and Japanese agreement. In this study, computational fluid dynamics, code FLUENT, was used on the two geometry of the Flow Straighteners which were designed for facility of EVEDA. According the analyzed results, they are crified that the flow turbulent kinetic energy has been generated in the junction between bend to Flow Straightener and bend section of piping, and that, it was found to exhibit rectification ability even on shortage geometry in the flow direction of Flow Straightner with margin under the operating condition that are currently scheduled of Lithium Test Loop.
Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.
no journal, ,
Shobu, Takahisa; Akita, Koichi; Shiro, Ayumi; Fujishiro, Tomoyuki*; Kiriyama, Koji*; Kumagai, Masayoshi*; Hisamori, Noriyuki*
no journal, ,
