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Kuroda, Shigeki*; Kamei, Gento
Genshiryoku Bakkuendo Kenkyu, 13(1), p.31 - 35, 2006/10
Long half-life low heat generating radioactive waste (TRU waste) containing higher amount of radionuclide is considered to be disposed into a geologic formation. As an optimized geologic disposal of the waste, a technical possibility of co-disposal with high-level radioactive waste is being studied. An assessment result shows that a co-disposal is possible in a Japanese representative geologic environment by setting these repositories at a certain distance apart because reciprocal influences can be avoided. Atomic Energy Commission of Japan deliberated on the result and judged that the co-disposal concept described in the 2nd progress TRU report has a technical possibility. On the other side, future studies are required from the view points of (1) more reliable assessment of co-disposal, (2) expansion of generic assessment basis, and (3) flexible correspondence for wide geologic environmental conditions. This article shows a current status of the investigations of TRU waste disposal including an overview of the disposal concept and concrete items for the future studies.
Kurikami, Hiroshi; Kunimaru, Takanori; Funaki, Hironori
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Tanaka, Tadao; Yamaguchi, Tetsuji; Iida, Yoshihisa; Kimura, Yuichiro; Taki, Hiroshi; Fujiwara, Takeshi; Ueda, Masato*; Mukai, Masayuki; Yamada, Fumika; Mizuno, Tsuyoshi; et al.
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Sekioka, Yasushi; Takeda, Seiji; Kimura, Hideo; Yamaguchi, Tetsuji; Oe, Toshiaki*; Nagasaki, Shinya*; Sasaki, Takayuki*; Kozaki, Tamotsu*; Inagaki, Yaohiro*
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Hanamuro, Takahiro; Nohara, Tsuyoshi; Umeda, Koji; Moriya, Toshifumi; Nakatsuka, Noboru
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Geoscientific research is performed as a basis of the research and development on the geological disposal technology of high-level radioactive waste in the Tono Geoscience Center, JAEA. In this seminar, we report on the current status of the research on long-term stability of the geological environment among research topics set by the geoscientific research.
Kato, Tomoko; Oi, Takao
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no abstracts in English
Maekawa, Keisuke; Karasaki, Kenji*; Ito, Kazumasa*
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As a study to comprehend geological environment, we examined numerical analysis in order to understand the behavior of saltwater intrusion. This is an important study for safety assessment of high level radioactive waste geologic disposal. We made sense a relation between an extent of numerical dispersion and various grid spacing in analytical region. And the analytical code was verified with an experiment under the simple condition.
Tajima, Takatoshi*; Shimmura, Akira*; Mihara, Morihiro
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no abstracts in English
Hayashi, Maki*; Satake, Kenji*; Sasamoto, Hiroshi; Yoshikawa, Hideki; Yui, Mikazu
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In the analysis of radionuclides migration in the performance assessment of geological disposal system, the release of radionuclides from vitrified glass is considered as the source-term for radionuclides migration, and model development and quantitative assessment of glass dissolution are necessary for the analysis. For a realistic assessment of radionuclides release from the vitrified waste glass, further research to improve understanding based on the scientific basis and development of robust glass dissolution model are important. As one of the tool to reflect these researches, we have been developing the Glass Dissolution Rate Database. This database has information on the dissolution behavior of glass. We researched the documents about the leaching tests of HLW glass, and registered the data of normalized elemental mass loss from HLW glass with experimental conditions. At present the prototype database has been developed using Microsoft Access.
Wada, Ryutaro*; Yamamoto, Seiichi*; Masuda, Kaoru*; Meguro, Yoshihiro; Tomioka, Osamu; Yamamoto, Ichiro*
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no abstracts in English
Umeki, Hiroyuki; Yui, Mikazu; Shimizu, Kazuhiko
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no abstracts in English
Nakayama, Shinichi; Nagasaki, Shinya*
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no abstracts in English