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Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Nakamichi, Masaru; Katsuyama, Kozo; Iwamatsu, Shigemi; Hasegawa, Teiji; Kodaka, Hideo; Takatsu, Hideyuki; et al.
JAEA-Technology 2009-007, 168 Pages, 2009/03
In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been being performed irradiation experiments of lithium titanate (LiTiO), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes (1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and (2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, datailed specifications and the installation methods were examined, based on results of a conceptual design and basic design. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility.
Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Kodaka, Hideo; Katsuyama, Kozo; Kitajima, Toshio; Takahashi, Kozo; Tsuchiya, Kunihiko; Nakamichi, Masaru; et al.
JAEA-Technology 2008-010, 68 Pages, 2008/03
In-pile functional tests of breeding blankets for fusion reactors have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in ITER. The present report describes a conceptual investigation and a basic design of the dismantling process for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA. In the present design, the irradiation capsule is cut by a band saw; the released tritium is recovered safely by a purge-gas system, and is consolidated into a radioactive waste form. Furthermore, adoption of the inner-box enclosing the dismantling apparatus has brought a prospect to be able to utilize an existing hot cell (beta- cell) equipped with usual wall material permeable to tritium, without extensive refurbishing of the cell. Thus, the present study has indicated the feasibility of the present dismantling process for the irradiated JMTR capsules containing tritium.
Ouchi, Nobuo; Akaoka, Nobuo*; Asano, Hiroyuki*; Chishiro, Etsuji; Namekawa, Yuya*; Suzuki, Hiroyuki*; Ueno, Tomoaki*; Noguchi, Shuichi*; Kako, Eiji*; Ouchi, Norihito*; et al.
Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.175 - 183, 2005/11
no abstracts in English
Kako, Eiji*; Noguchi, Shuichi*; Ouchi, Norihito*; Shishido, Toshio*; Akaoka, Nobuo*; Kobayashi, Hideki*; Ouchi, Nobuo; Ueno, Tomoaki*; Hara, Hiroshi*; Matsuoka, Masanori*; et al.
Proceedings of 9th European Particle Accelerator Conference (EPAC 2004) (CD-ROM), p.1042 - 1044, 2004/07
no abstracts in English
Ouchi, Norihito*; Kako, Eiji*; Noguchi, Shuichi*; Shishido, Toshio*; Tsuchiya, Kiyosumi*; Akaoka, Nobuo*; Kobayashi, Hideki*; Ouchi, Nobuo; Ueno, Tomoaki*; Hara, Hiroshi*; et al.
Proceedings of 9th European Particle Accelerator Conference (EPAC 2004), p.1033 - 1035, 2004/00
no abstracts in English
Kikuchi, Shusuke*; Umenyi, A. V.*; Inada, Kazuki*; Kawashima, Akihiro*; Noguchi, Katsuya*; Sasaki, Tomoyuki*; Miura, Kenta*; Hanaizumi, Osamu*; Yamamoto, Shunya; Kawaguchi, Kazuhiro; et al.
no journal, ,
Light emission around a wavelength () of 500 nm from SiO substrates implanted with Si and C ions and annealed at 1100C has been reported. In this report, we investigated photoluminescence (PL) properties of SiO substrates implanted with Si and C ions and annealed at the lower temperature of 700C. PL peaks by Si-ion implantation were observed around = 650 nm, and PL peaks by C-ion implantation were observed around = 450 nm from SiO substrates annealed at 700C. The PL peak wavelength became shorter by increasing the ratio of C to Si ions. Consequently, it was confirmed that it is possible to control the emission wavelength by the ratio of C to Si ions. Our samples showed typical light-emission though the annealing temperature was lower than the temperature reported by other groups.
Ozawa, Yusuke*; Kubota, Hitoshi*; Miura, Kenta*; Hanaizumi, Osamu*; Noguchi, Katsuya*; Sato, Takahiro; Ishii, Yasuyuki; Koka, Masashi; Takano, Katsuyoshi*; Okubo, Takeru; et al.
no journal, ,
Inada, Kazuki*; Kawashima, Akihiro*; Kano, Keisuke*; Noguchi, Katsuya*; Miura, Kenta*; Hanaizumi, Osamu*; Yamamoto, Shunya; Kawaguchi, Kazuhiro*; Yoshikawa, Masahito
no journal, ,
It is reported that Si and C ions implanted SiO substrates emit blue light. In this paper, we are studying photoluminescence (PL) properties of SiO substrates implanted with Si and C ions on various conditions. Si and C ions were implanted into an SiO substrate by using a 400-kV ion implanter at JAEA/Takasaki. The Si-ion implantation energy was 150 keV, and the implantation dose was 5.010 ions/cm. The C-ion implantation energy was 75 keV, and the implantation dose was 3.010 ions/cm. The samples were subsequently annealed at 700C for 25 min in air, after 1000C for 25 min in air. The results of PL measurements show that the PL peak wavelength became shorter by increasing the ratio of C ions to Si ions. Consequently, it was confirmed that the emission wavelength can be controlled by hanging the ratio of C and Si.
Kano, Keisuke*; Saruya, Ryota*; Kawabata, Shunsuke*; Araki, Jun*; Noguchi, Katsuya*; Kada, Wataru*; Miura, Kenta*; Kato, Hijiri*; Sato, Takahiro; Koka, Masashi; et al.
no journal, ,