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Nakashima, Yosuke*; Takeda, Hisahito*; Ichimura, Kazuya*; Hosoi, Katsuhiro*; Oki, Kensuke*; Sakamoto, Mizuki*; Hirata, Mafumi*; Ichimura, Makoto*; Ikezoe, Ryuya*; Imai, Tsuyoshi*; et al.
Journal of Nuclear Materials, 463, p.537 - 540, 2015/08
Times Cited Count:18 Percentile:82.74(Materials Science, Multidisciplinary)Nakashima, Yosuke*; Sakamoto, Mizuki*; Yoshikawa, Masayuki*; Oki, Kensuke*; Takeda, Hisahito*; Ichimura, Kazuya*; Hosoi, Katsuhiro*; Hirata, Mafumi*; Ichimura, Makoto*; Ikezoe, Ryuya*; et al.
Proceedings of 25th IAEA Fusion Energy Conference (FEC 2014) (CD-ROM), 8 Pages, 2014/10
Hemmi, Tsutomu; Nishimura, Arata*; Matsui, Kunihiro; Koizumi, Norikiyo; Nishijima, Shigehiro*; Shikama, Tatsuo*
AIP Conference Proceedings 1574, p.154 - 161, 2014/01
Times Cited Count:6 Percentile:92.73Japan Atomic Energy Agency (JAEA), as Japan Domestic Agency, has responsibility to procure 9 ITER Toroidal Field (TF) coils. The insulation system of the ITER TF coils consists of 3 layers of insulations, which are a conductor insulation, a double-pancake (DP) insulation and a ground insulation, composed of multi-layer glass/polyimide tapes impregnated a resin. The ITER TF coils are required to withstand an irradiation of 10 MGy from -ray and neutrons since the ITER TF coils is exposed by first neutron ( 0.1 MeV) of 10 n/m during the operation of 20 years in the ITER. Cyanate-ester/epoxy blended resins and bonded glass/polyimide tapes are developed as insulation materials to realize the required radiation-hardness for the insulation of the ITER TF coils. To evaluate the radiation-hardness of the developed insulation materials, the inter-laminar shear strength of glass-fiber reinforced plastics (GFRP) fabricated using developed insulation materials is measured as one of most important mechanical properties before/after the irradiation in a fission reactor of JRR-3. As a result, it is demonstrated that the GFRPs using the developed insulation materials have a sufficient performance to apply the ITER TF coil insulation.
Inaba, Yoshitomo; Tsuchiya, Kunihiko; Shikama, Tatsuo*; Nishimura, Arata*; Kawamura, Hiroshi
Fusion Engineering and Design, 86(2-3), p.134 - 140, 2011/03
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)The Japan Materials Testing Reactor (JMTR) of the Japan Atomic Energy Agency is a testing reactor with first criticality in March 1968. The reactor has been utilized for various neutron irradiation tests on nuclear fuels and materials, as well as for radioisotope production. The operation of JMTR stopped temporarily in August 2006 for refurbishment and improvement. The renewed JMTR will resume operation in Japanese fiscal year 2011. For the resumption of the new JMTR, the new irradiation facilities, the usability improvements, the target, and the expected roles of the new JMTR have been discussed. As one of the new irradiation facilities, the cryogenic irradiation facility, which is used for the investigation on the low-temperature irradiation behavior of materials such as superconducting magnet materials for fusion reactors, has been desired. In this study, the feasibility of low-temperature irradiation tests with the cryogenic irradiation facility was investigated, and the conceptual design of the facility was carried out. As a result, it was found that irradiation tests at temperatures below 20 K for the development of the superconducting magnet materials can be realized by the installation of an irradiation capsule into an irradiation hole with low heating and by the adoption of vacuum jacketed tubes to connect between the capsule and a cooling system.
Nishimura, Arata*; Izumi, Yoshinobu*; Nishijima, Shigehiro*; Hemmi, Tsutomu; Koizumi, Norikiyo; Takeuchi, Takao*; Shikama, Tatsuo*
AIP Conference Proceedings 1219, p.127 - 134, 2010/04
Times Cited Count:1 Percentile:50.39A GFRP with cyanate ester resin was fabricated and neutron irradiation tests up to 110 n/m of fast neutron with over 0.1 MeV energy were carried out in fission reactor. The fabrication process of cyanate ester GFRP was established and a collaboration network to perform investigations on irradiation effect of superconducting magnet materials was constructed. Three kinds of samples were fabricated. The first was CTD403 GFRP made by NIFS, the second was (cyanate ester + epoxy) GFRP provided by Toshiba, and the last was CTD403 GFRP made by Toshiba. The irradiation was carried out at JRR-3 in Japan Atomic Energy Agency using Rabbit capsules. After the irradiation, short beam tests were conducted at room temperature and 77 K and interlaminar shear strength (ILSS) was evaluated. The irradiation of 110 n/m increased ILSS a little but 110 n/m irradiation decreased ILSS to around 50 MPa. These tendencies were observed in all three kinds of GFRPs.
To, Kentaro*; Shikama, Tatsuo*; Nagata, Shinji*; Tsuchiya, Bun*; Yamauchi, Michinori; Nishitani, Takeo
Journal of Nuclear Materials, 367-370(2), p.1128 - 1132, 2007/08
Times Cited Count:6 Percentile:42.6(Materials Science, Multidisciplinary)no abstracts in English
Nagata, Shinji*; Yamamoto, Shunya; Inoue, Aichi*; Tsuchiya, Bun*; To, Kentaro*; Shikama, Tatsuo*
Journal of Nuclear Materials, 367-370(2), p.1009 - 1013, 2007/08
Times Cited Count:30 Percentile:88.45(Materials Science, Multidisciplinary)no abstracts in English
To, Kentaro*; Shikama, Tatsuo*; Nagata, Shinji*; Tsuchiya, Bun*; Yamauchi, Michinori; Nishitani, Takeo
Measurement Science and Technology, 17(5), p.955 - 959, 2006/05
Times Cited Count:6 Percentile:43.74(Engineering, Multidisciplinary)The effect of photobleaching on radiation-induced transmission loss of fused-silica-core optical fibres was examined under Co -ray and 14 MeV neutron irradiation. In the visible wavelength range, the radiation-induced transmission loss could be reduced by photobleaching under both types of irradiation. It is considered that the number of radiation-induced defects such as E' centre and NBOHC that cause optical absorption was reduced by photobleaching. For using optical fibres in the visible wavelength range as light guides or image guides, photobleaching is an effective technique to improve their radiation resistance. However, a so-called microbending loss is induced by radiation in the entire wavelength range. The loss response to photobleaching was different under -ray and fast-neutron irradiation. The loss under the -ray irradiation increased due to photobleaching, while that under the fast-neutron irradiation decreased. It is considered that there are multiple reasons for the radiation-enhanced microbending loss. In general, it is concluded that the photobleaching technique is effective in improving the radiation resistance of fused-silica-core optical fibres under neutron and moderate flux radiation environments.
Nagata, Shinji*; Yamamoto, Shunya; Tokunaga, Kazutoshi*; Tsuchiya, Bun*; To, Kentaro*; Shikama, Tatsuo*
Nuclear Instruments and Methods in Physics Research B, 242(1-2), p.553 - 556, 2006/01
Times Cited Count:7 Percentile:47.55(Instruments & Instrumentation)no abstracts in English
Takatsu, Hideyuki; Sato, Kazuyoshi; Hamada, Kazuya; Nakahira, Masataka; Suzuki, Satoshi; Nakajima, Hideo; Kuroda, Toshimasa*; Nishitani, Takeo; Shikama, Tatsuo*; Shu, Wataru
Journal of Nuclear Materials, 329-333(1), p.178 - 182, 2004/08
Times Cited Count:2 Percentile:17.2(Materials Science, Multidisciplinary)This paper presents an overview on ITER-supporting materials research and development activities and major achievements in Japan during the period from the Co-ordinated Technical Activities to date. In view of the completed engineering design of ITER during the Engineering Design Activities period, research and development efforts since then have been focused: those for reduction of component fabrication cost; those in support of domestic preparations of a structural technical code for construction; those necessary for operation, and been extended to component-level testing rather than pure material testing. They cover materials Research and Development for in-vessel components, vacuum vessel, cryogenic steels of superconducting mgnet and diagnostics components. Major achievements in each research and development area are highlighted and their impact or implication to the design, construction and operation of ITER is presented.
Nishitani, Takeo; *; Ikeda, Yujiro; Ishitsuka, Etsuo; Kakuta, Tsunemi; Kasai, Satoshi; Kawamura, Hiroshi; Morita, Yosuke; Nagashima, Akira; Nakamichi, Masaru; et al.
JAERI-Research 98-053, 105 Pages, 1998/10
no abstracts in English
Kakuta, Tsunemi; *; *;
Fusion Engineering and Design, 41, p.201 - 205, 1998/00
Times Cited Count:45 Percentile:94.62(Nuclear Science & Technology)no abstracts in English
Kakuta, Tsunemi; Sakasai, Kaoru; *; *;
Journal of Nuclear Materials, 258-263, p.1893 - 1896, 1998/00
Times Cited Count:20 Percentile:81.52(Materials Science, Multidisciplinary)no abstracts in English