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JAEA Reports

Preliminary study for long life as beryllium reflector, 1; Fabrication of irradiation capsule and dismounted device of capsule

Hanawa, Yoshio; Taguchi, Taketoshi; Tsuboi, Kazuaki; Saito, Takashi; Ishikawa, Kazuyoshi; Watahiki, Shunsuke; Tsuchiya, Kunihiko

JAEA-Technology 2008-039, 53 Pages, 2008/06

JAEA-Technology-2008-039.pdf:6.18MB

Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. Beryllium frames and beryllium reflectors, which have been utilized as neutron reflector in Japan Materials Testing Reactor (JMTR) in JAEA, were fabricated beryllium metals of S-200F grade. Especially, it is necessary to exchange the beryllium frames every fixed period and there frames were exchanged six times up to the JMTR operation periods of 165 cycles. Therefore, preliminary irradiation test of beryllium metals was performed from 162 to 165 cycles of JMTR operations as a part of development on long life of beryllium reflectors. Two kinds of beryllium metals (S-200F and S-65C) were prepared in this test. This report is described the design study and fabrication of irradiation capsule of beryllium metals and dismount device of irradiation capsule.

JAEA Reports

Development of module for TRU high temperature chemistry (Joint research)

Minato, Kazuo; Akabori, Mitsuo; Tsuboi, Takashi; Kurobane, Shiro; Hayashi, Hirokazu; Takano, Masahide; Otobe, Haruyoshi; Misumi, Masahiro*; Sakamoto, Takuya*; Kato, Isao*; et al.

JAERI-Tech 2005-059, 61 Pages, 2005/09

JAERI-Tech-2005-059.pdf:20.67MB

An experimental facility called the Module for TRU High Temperature Chemistry (TRU-HITEC) was installed in the Back-end Cycle Key Elements Research Facility (BECKY) of the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) for the basic studies of the behavior of the transuranium elements (TRU) in pyrochemical reprocessing and oxide fuels. TRU-HITEC consists of three alpha/gamma cells shielded by steel and polyethylene and a glove box shielded by leaded acrylic resin, where experimental apparatuses have been equipped and a high purity argon gas atmosphere is maintained. In the facility 10 g of $$^{241}$$Am as well as the other TRU of Np, Pu and Cm can be handled. This report summarizes the outline, structure, performance and interior apparatuses of the facility, and is the result of the joint research between the Japan Atomic Energy Research Institute and three electric power companies of Tokyo Electric Power Co., Tohoku Electric Power Co. and the Japan Atomic Power Co.

Journal Articles

Alpha-decay damage of Cm-doped Perovskite

; ; Tsuboi, Takashi; E.R.Vance*; B.D.Begg*; K.P.Hart*

Materials Research Society Symposium Proceedings, Vol.353, 0, p.1405 - 1412, 1995/00

no abstracts in English

Journal Articles

Rietveld analysis of phase separation in annealed and leach tested Cm-doped Perovskite

White, T. J.*; ; Tsuboi, Takashi

Materials Research Society Symposium Proceedings, Vol.353, 0, p.871 - 878, 1995/00

no abstracts in English

Journal Articles

$$alpha$$-decay damage effects in curium-doped titanate ceramic containing sodium-free high-level nuclear waste

; ; M.W.A.Stewart*; Tsuboi, Takashi; *; E.R.Vance*; K.P.Hart*; Togashi, Yoshihiro; Kanazawa, Hiroyuki; C.J.Ball*; et al.

Journal of the American Ceramic Society, 77(9), p.2255 - 2264, 1994/00

 Times Cited Count:30 Percentile:80.41(Materials Science, Ceramics)

no abstracts in English

Oral presentation

Distribution and migration of U, Th and trace elements in Toki granite

Tsuboi, Mariko*; Honda, Teruyuki*; Iwatsuki, Teruki; Mizuno, Takashi

no journal, , 

no abstracts in English

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