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Journal Articles

Present and future studies for geological disposal of long half life radionuclides bearing low feverish radioactive waste

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.

Oral presentation

Hydrogeological environmental model in surface-based investigations of Horonobe URL project

Kurikami, Hiroshi; Kunimaru, Takanori; Funaki, Hironori

no journal, , 

no abstracts in English

Oral presentation

Experimental research for long term evaluation on radioactive waste disposal; Progress in 2006

Tanaka, Tadao; Yamaguchi, Tetsuji; Iida, Yoshihisa; Kimura, Yuichiro; Taki, Hiroshi; Fujiwara, Takeshi; Ueda, Masato*; Mukai, Masayuki; Yamada, Fumika; Mizuno, Tsuyoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of database for long-term safety assessment of radioactive waste disposal

Sekioka, Yasushi; Takeda, Seiji; Kimura, Hideo; Yamaguchi, Tetsuji; Oe, Toshiaki*; Nagasaki, Shinya*; Sasaki, Takayuki*; Kozaki, Tamotsu*; Inagaki, Yaohiro*

no journal, , 

no abstracts in English

Oral presentation

Current status of the study on the long-term stability of the geological environment

Hanamuro, Takahiro; Nohara, Tsuyoshi; Umeda, Koji; Moriya, Toshifumi; Nakatsuka, Noboru

no journal, , 

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.

Oral presentation

Extraction of future research items and perspectives for biosphere assessment of geological disposal

Kato, Tomoko; Oi, Takao

no journal, , 

no abstracts in English

Oral presentation

An Examination on saltwater intrusion in geological environment

Maekawa, Keisuke; Karasaki, Kenji*; Ito, Kazumasa*

no journal, , 

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.

Oral presentation

Study on applicability of low alkaline shotcrete

Tanai, Kenji

no journal, , 

no abstracts in English

Oral presentation

Hydraulic properties of compacted bentonite under high alkaline and nitrate fluids

Tajima, Takatoshi*; Shimmura, Akira*; Mihara, Morihiro

no journal, , 

no abstracts in English

Oral presentation

Development of glass dissolution database

Hayashi, Maki*; Satake, Kenji*; Sasamoto, Hiroshi; Yoshikawa, Hideki; Yui, Mikazu

no journal, , 

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.

Oral presentation

Separation and recovery of uranium from radioactive solid waste by supercritical carbon dioxide leaching method

Wada, Ryutaro*; Yamamoto, Seiichi*; Masuda, Kaoru*; Meguro, Yoshihiro; Tomioka, Osamu; Yamamoto, Ichiro*

no journal, , 

no abstracts in English

Oral presentation

"Coordination executive" R&D programme of HLW geological disposal

Umeki, Hiroyuki; Yui, Mikazu; Shimizu, Kazuhiko

no journal, , 

no abstracts in English

Oral presentation

Invitation to radioactive waste disposal research network

Nakayama, Shinichi; Nagasaki, Shinya*

no journal, , 

no abstracts in English

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