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Journal Articles

Investigation of chemical state of uranium included in simulated waste glass

Nagai, Takayuki; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Okamoto, Yoshihiro

2020-Nendo "Busshitsu, Debaisu Ryoiki Kyodo Kenkyu Kyoten" Oyobi "Hito, Kankyo To Busshitsu O Tsunagu Inobeshion Soshutsu Dainamikku, Araiansu" Kenkyu Seika, Katsudo Hokokusho (CD-ROM), 1 Pages, 2021/11

no abstracts in English

JAEA Reports

Corrosion behavior of a simulated high-level radioactive waste glass under oxic and anoxic conditions

Maeda, Toshikatsu; Inagaki, Yaohiro*; Bamba, Tsunetaka; *

JAERI-Research 95-019, 18 Pages, 1995/03

JAERI-Research-95-019.pdf:0.86MB

no abstracts in English

JAEA Reports

None

; Sumiya, Shuichi;

PNC TN8450 94-006, 28 Pages, 1994/12

no abstracts in English

Oral presentation

The Effect of carbonate ion on the dissolution of UO$$_{2}$$ pellet

Moroi, Yuriko*; Kirishima, Akira*; Akiyama, Daisuke*; Sato, Nobuaki*; Kitamura, Akira; Kimuro, Shingo

no journal, , 

Direct disposal of spent nuclear fuel is considered as an alternative option of geological disposal of high level radioactive wastes. In this case, the dissolution speed of uranium should be one of the most important parameter. In this study, the dissolution behavior of UO$$_{2}$$ in the simulated groundwater contains high concentration of carbonate ion was investigated, then, it was revealed that uranium dissolution was promoted by the carbonate ion.

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