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Irisawa, Keita; Nakagawa, Akinori; Onizawa, Takashi*; Kogawara, Takafumi*; Hanada, Keiji; Meguro, Yoshihiro
Proceedings of 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2013) (CD-ROM), 5 Pages, 2013/09
Times Cited Count：1 Percentile：59.66(Engineering, Environmental)Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*
Fusion Engineering and Design, 86(12), p.2904 - 2907, 2011/12
Times Cited Count：3 Percentile：25.34(Nuclear Science & Technology)no abstracts in English
Wakai, Eiichi; Kikuchi, Takayuki; Kogawara, Takafumi; Kimura, Haruyuki; Yokomine, Takehiko*; Kimura, Akihiko*; Nogami, Shuhei*; Kurishita, Hiroaki*; Saito, Masahiro*; Nishimura, Arata*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03
Japanese activities of test facilities in IFMIF-EVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) project have three subjects of engineering design of post irradiation examination (PIE) facilities, small specimen test technique (SSTT), and engineering design of high flux test module (HFTM), and this paper is summarized about present status. Functional analysis and design of 2-D and 3-D models of PIE facility were performed. In HFTM, as materials of heater, W-3Re alloy and/or SiC/SiC composite were selected in the points of high temperature materials, fabrication technology and some suitable properties such as resistance of thermal shock, high temperature re-crystallization, ductility, resistance of irradiation degradation, and low-activation. In SSTT, a test machine of fracture toughness was designed and developed for small specimens with 10 mm square, and it had high accuracy controllability for stress and displacement.
Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki
Journal of Plasma and Fusion Research SERIES, Vol.9, p.242 - 247, 2010/08
Recent progress of preliminary engineering design of post irradiation examination (PIE) facilities of IFMIF-EVEDA (International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities) was summarized. The PIE Facilities have mainly hot cells and preparation rooms for some examinations and tests of the materials irradiated in the high-, medium- and low-flux test modules, back plate of Li target, and the others of IFMIF. In this study a basic functional analysis was performed, and handling process of specimen reloading and radiation-shielding wall in hot cells was also evaluated. Based on the results, a layout of PIE facilities was designed.
Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yokomine, Takehiko*; Molla, J.*; Yamamoto, Michiyoshi
no journal, ,
no abstracts in English
Nakagawa, Akinori; Kogawara, Takafumi; Onizawa, Takashi; Meguro, Yoshihiro
no journal, ,
Engineering test of high concentrated sodium nitrate separation by electrodialysis with membrane was conducted. In this test, transferation efficiency, electric power consumption, ion selectivity and composition of separated solution were researched.
Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Nakamura, Kazuyuki; Molla, J.*
no journal, ,
no abstracts in English
Nakagawa, Akinori; Kogawara, Takafumi; Onizawa, Takashi*; Hanada, Keiji; Nakayama, Takuya; Meguro, Yoshihiro
no journal, ,
no abstracts in English
Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*; Kimura, Akihiko*; Kasada, Ryuta*; Kim, B.*; Nogami, Shuhei*; Hasegawa, Akira*; et al.
no journal, ,
no abstracts in English
Meguro, Yoshihiro; Nakagawa, Akinori; Kogawara, Takafumi; Onizawa, Takashi
no journal, ,
Based on basic experiments of sodium nitrate separation by electrodialysis with membrane, an apparatus concept was established and an engineering scale equipment was built. A designed separation ability was showed in a performance test.
Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Nakamura, Kazuyuki; Sugimoto, Masayoshi
no journal, ,
no abstracts in English
