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Journal Articles

Nitrogen hot trap design and manufactures for lithium test loop in IFMIF/EVEDA project

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

BB2015-1982.pdf:2.03MB

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

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:36.81(Nuclear Science & Technology)

Journal Articles

Development of lithium target system in engineering validation and engineering design activity of the International Fusion Materials Irradiation Facility (IFMIF/EVEDA)

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

Journal Articles

IFMIF/EVEDA lithium test loop; Design and fabrication technology of target assembly as a key component

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:36 Percentile:84.88(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.

Journal Articles

Engineering design and construction of IFMIF/EVEDA lithium test loop; Design and fabrication of integrated target assembly

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.

Oral presentation

Strain measurement of aged duplex stainless steel using SR white X-ray

Kiriyama, Koji; Shobu, Takahisa; Shibano, Junichi*; Fujishiro, Tomoyuki; Kaneko, Hiroshi; Miura, Setsuo*

no journal, , 

Oral presentation

In-situ strain distribution using synchrotron radiation under high temperature and high pressure water

Fujishiro, Tomoyuki; Shobu, Takahisa; Terasawa, Michitaka*; Yamamoto, Atsushi*; Kiriyama, Koji*; Nakahigashi, Shigeo*; Hasegawa, Tadayuki*

no journal, , 

no abstracts in English

Oral presentation

Internal strain distribution of laser peened Ti-alloy rod studied by high energy synchrotron radiation X-rays

Shobu, Takahisa; Akita, Koichi; Shiro, Ayumi; Fujishiro, Tomoyuki*; Kiriyama, Koji*; Kumagai, Masayoshi*; Hisamori, Noriyuki*

no journal, , 

Oral presentation

Progress of engineering design in IFMIF-EVEDA project

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

Oral presentation

A Research on computation fluid dynamics (CFD) to optimize the designing of flow straightener of IFMIF/EVEDA liquid Lithium target assembly

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$$^{-3}$$ 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.

Oral presentation

An Estimation for flow straighteners of lithium target assembly in IFMIF/EVEDA facility by computational fluid dynamics (CFD)

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.

Oral presentation

Development status of lithium target and test facilities in IFMIF/EVEDA project

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

Oral presentation

CFD analysis for lithium flow in the IFMIF/EVEDA target assembly

Fujishiro, Koji; Ida, Mizuho; Tsuji, Yoshiyuki*; Wakai, Eiichi; Groeschel, F.*; Kondo, Hiroo; Kanemura, Takuji; Sugimoto, Masayoshi; Nishitani, Takeo

no journal, , 

no abstracts in English

Oral presentation

Progress and scheme of IFMIF/EVEDA project; Lithium target facility

Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.

no journal, , 

14 (Records 1-14 displayed on this page)
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