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Sawaguchi, Takuma; Yamaguchi, Tetsuji; Iida, Yoshihisa; Tanaka, Tadao; Kitagawa, Isamu
Clay Minerals, 48(2), p.411 - 422, 2013/05
Times Cited Count：2 Percentile：6.52(Chemistry, Physical)Diffusive transport of Cs
in compacted sand-bentonite mixtures was studied by a through diffusion method. Experiments were performed under variable aqueous compositions. Effective diffusivity (
) values of 5.2E-10
5.9E-9 m
s
were obtained. The variation was somewhat large in the values. Apparent diffusivity (
) values, on the other hand, were 2.0E-12 
6.2E-12 m s, which shows small variation. The results indicate that, in applying Fick's 1st law of diffusion, diffusive flux is proportional to the apparent concentration gradient of Cs in the sand-bentonite mixture rather than the gradient of Cs concentration in pore water. Since the apparent concentration gradient in sand-bentonite mixtures is nearly equal to the gradient of adsorbed Cs, diffusion of Cs under adsorbed state would be the main mechanism of diffusion of Cs in sand-bentonite mixtures.
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.
Maeda, Toshikatsu; Bamba, Tsunetaka*; Mizuno, Tsuyoshi*; Terakado, Shogo; Kitagawa, Isamu; Numata, Masami
Haikibutsu Gakkai Rombunshi, 17(4), p.271 - 281, 2006/07
no abstracts in English
Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro; Sekino, Hajime; Koya, Toshio; Kitagawa, Isamu; Ishikawa, Akiyoshi; Tomita, Takeshi;
Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00
no abstracts in English
CMinato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; Sekino, Hajime; Kitagawa, Isamu; Mita, Naoaki
Journal of Nuclear Materials, 249(2-3), p.142 - 149, 1997/00
Times Cited Count：60 Percentile：95.93(Materials Science, Multidisciplinary)no abstracts in English
Tsukada, Takashi; Shiba, Kiyoyuki; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; Itonaga, Fumio; Ishikawa, Akiyoshi
JAERI-M 92-169, 26 Pages, 1992/11
no abstracts in English
Shiba, Kiyoyuki; Tsukada, Takashi; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; ; Itonaga, Fumio; et al.
JAERI-M 92-166, 27 Pages, 1992/11
no abstracts in English
Yanagisawa, Kazuaki; ; Kitagawa, Isamu; Iida, Shozo; Ito, Tadaharu; Amano, Hidetoshi
JAERI-M 91-202, 33 Pages, 1991/11
no abstracts in English
Yanagisawa, Kazuaki; ; Sasajima, Hideo; ; ; Ishijima, Kiyomi; ; ; ; ; et al.
JAERI-M 90-091, 171 Pages, 1990/06
no abstracts in English
Numata, Masami; Kato, Chiaki; Motooka, Takafumi; Endo, Shinya; Kitagawa, Isamu; Kizaki, Minoru; Yamamoto, Masahiro; Kiuchi, Kiyoshi
no journal, ,
We estimated environment assisted cracking of zirconium such as the unclear fuel dissolver in spent unclear fuel solution and considered the cold simulated solution with substituted similar oxidization ions for trans-uranium (TRU) and fission products (FP) and difference between the cold simulated solution and the hot spent unclear fuel. In addition, we considered radiation effect of 
ray under irradiation of cobalt-60 to simulate closely the dissolver condition. In this report, we confirmed that the cold simulated solution is appropriate solution to substitute for the spent nuclear fuel solution and radiation of ray doesn't accelerate environment assisted cracking of zirconium.
Numata, Masami; Komiya, Tomokazu; Sakuraba, Naotoshi; Usami, Koji; Kitagawa, Isamu; Tomita, Takeshi*
no journal, ,
no abstracts in English
Matsui, Hiroki; Honda, Junichi; Ono, Katsuto; Kitagawa, Isamu; Owada, Isao; Kikuchi, Hiroyuki
no journal, ,
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 
and 
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.
