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Journal Articles

Thermalconductivities of (Np,Am)N and (Pu,Am)N solid solutions

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Miyata, Seiichi; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

IOP Conference Series; Materials Science and Engineering, 9, p.012017_1 - 012017_8, 2010/05

 Times Cited Count:2 Percentile:73.44

The thermal diffusivities and heat capacities of transuranium nitride solid solutions, (Np,Am)N and (Pu,Am)N, were measured by using a laser flash method and a drop calorimetry, respectively. The thermal conductivities of these samples were determined from the measured thermal diffusivities, heat capacities and bulk densities. The thermal conductivities of (Np,Am)N and (Pu,Am)N increased with temperature over the temperature range investigated. The increases in the thermal conductivities were probably due to the increase of electrical components. In addition, the thermal conductivities of (Np,Am)N and (Pu,Am)N decreased with increasing Am contents. It could be considered that the decreases in the thermal conductivities correspond to the lowering of electronic contribution.

JAEA Reports

Replacement technology for front acrylic panels of a large-sized glove box using bag-in / bag-out method

Sakuraba, Naotoshi; Numata, Masami; Komiya, Tomokazu; Ichise, Kenichi; Nishi, Masahiro; Tomita, Takeshi; Usami, Koji; Endo, Shinya; Miyata, Seiichi; Kurosawa, Tatsuya; et al.

JAEA-Technology 2009-071, 34 Pages, 2010/03

JAEA-Technology-2009-071.pdf:21.07MB

As a part of maintenance technology of a large-sized glove box for handling of TRU nuclides, we developed replacement technology for front acrylic panels using the bag-in/bag-out method and applied this technology to replace the deteriorated front acrylic panels at Waste Safety Testing Facility (WASTEF) in Nuclear Science Research Institute of Japan Atomic Energy Agency (JAEA). As a consequence, we could safely replace the front acrylic panels under the condition of continuous negative pressure only with partial decontamination of the glove box. We also demonstrated that the present technology is highly effective in points of safety, workability and cost as compared to the usual replacement technology for front acrylic panels of a glove box, where workers in an air-line suit replace directly the front acrylic panels in a green house.

JAEA Reports

Release behavior of fission products from irradiated dispersion fuel at high temperature

Iwai, Takashi; ; Nakagawa, Tetsuya; ; Miyata, Seiichi; Kawamata, Kazuo; Komukai, Bunsaku; Saito, Junichi; Itabashi, Yukio; ; et al.

JAERI-M 90-027, 28 Pages, 1990/02

JAERI-M-90-027.pdf:1.24MB

no abstracts in English

Oral presentation

Development of volume reduction equipment for radioactive waste

Ichise, Kenichi; Sakuraba, Naotoshi; Suzuki, Kazuhiro; Miyata, Seiichi; Komiya, Tomokazu; Nishi, Masahiro; Kitagawa, Isamu; Numata, Masami

no journal, , 

As a part of measures to reduce radioactive wastes, which are generated during operation and maintenance of Waste Safety Testing Facility (WASTEF), we developed volume reduction equipment for $$beta$$$$gamma$$ and $$alpha$$ wastes. In this presentation, we report manufacture of an experimental model, its operativeness & verification of reduction effect in a mock-up test, improvements, and application to actual radioactive wastes.

Oral presentation

Isotopic composition measurement of FP nuclides in spent LWR UO$$_{2}$$ fuel and nucleonics analysis, 2; Measurements of FP nuclides

Ito, Mitsuo; Fukaya, Hiroyuki; Ueno, Takashi; Miyata, Seiichi; Sonoda, Takashi; Usami, Hidehiko; Sakazume, Yoshinori; Kurosawa, Tatsuya; Kawasaki, Yasushi; Inagawa, Jun; et al.

no journal, , 

no abstracts in English

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