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Journal Articles

Diffusion of Cs, Np, Am and Co in compacted sand-bentonite mixtures; Evidence for surface diffusion of Cs cations

Sawaguchi, Takuma; Yamaguchi, Tetsuji; Iida, Yoshihisa; Tanaka, Tadao; Kitagawa, Isamu

Clay Minerals, 48(2), p.411 - 422, 2013/05

 Times Cited Count:2 Percentile:7.97(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 ($$D$$$$_{e}$$) values of 5.2E-10$$ sim$$ 5.9E-9 m$$^{2}$$ s$$^{-1}$$ were obtained. The variation was somewhat large in the $$D$$$$_{e}$$ values. Apparent diffusivity ($$D$$$$_{a}$$) values, on the other hand, were 2.0E-12 $$sim$$ 6.2E-12 m$$^{2}$$ s$$^{-1}$$, 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.

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.

Journal Articles

Dissolution behavior of slag in cement-equilibrated aqueous solutions

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

Journal Articles

ZrC-coated particle fuel for high temperature gas-cooled reactors

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

Journal Articles

Fission product release from ZrC-coated fuel particles during post-irradiation heating at 1800 and 2000$$^{circ}$$C

Minato, 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:57 Percentile:95.97(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Electrochemical corrosion behavior of spectrally tailored neutron irradiated stainless steel

Tsukada, Takashi; Shiba, Kiyoyuki; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; Itonaga, Fumio; Ishikawa, Akiyoshi

JAERI-M 92-169, 26 Pages, 1992/11

JAERI-M-92-169.pdf:2.76MB

no abstracts in English

JAEA Reports

Electrochemical corrosion behavior of stainless steel irradiated in FBR

Shiba, Kiyoyuki; Tsukada, Takashi; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; ; Itonaga, Fumio; et al.

JAERI-M 92-166, 27 Pages, 1992/11

JAERI-M-92-166.pdf:2.35MB

no abstracts in English

JAEA Reports

Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod

Yanagisawa, Kazuaki; ; Kitagawa, Isamu; Iida, Shozo; Ito, Tadaharu; Amano, Hidetoshi

JAERI-M 91-202, 33 Pages, 1991/11

JAERI-M-91-202.pdf:1.27MB

no abstracts in English

JAEA Reports

Technical report; Fabrication of PWR type rodlet fuel

Yanagisawa, Kazuaki; ; Sasajima, Hideo; ; ; Ishijima, Kiyomi; ; ; ; ; et al.

JAERI-M 90-091, 171 Pages, 1990/06

JAERI-M-90-091.pdf:6.33MB

no abstracts in English

Oral presentation

Corrosion mechanism of component materials used in nuclear fuel reprocessing plant, 4; Confirmation of environment assisted cracking of zirconium by hot laboratory tests

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 $$gamma$$ 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 $$gamma$$ ray doesn't accelerate environment assisted cracking of zirconium.

Oral presentation

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

Numata, Masami; Komiya, Tomokazu; Sakuraba, Naotoshi; Usami, Koji; Kitagawa, Isamu; Tomita, Takeshi*

no journal, , 

no abstracts in English

Oral presentation

Status of PIEs in the Department of Hot Laboratories and Facilities

Matsui, Hiroki; Honda, Junichi; Ono, Katsuto; Kitagawa, Isamu; Owada, Isao; Kikuchi, Hiroyuki

no journal, , 

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.

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