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Oral presentation

Estimation of source term for spent fuel disposal, 2; Effect of carbonate concentration on dissolution rate of UO$$_{2}$$ and spent fuel; A Review

Kitamura, Akira; Akahori, Kuniaki*

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Since dissolution rate of UO$$_{2}$$ matrices will be depend on carbonate concentration due to promoting oxidative dissolution of spent nuclear fuel by formation of carbonate complexes of uranium(VI), effect of carbonate concentration on dissolution rate of UO$$_{2}$$ and spent nuclear fuel has been reviewed. It is found that a systematic study on dissolution rate of UO$$_{2}$$ and/or spent fuel as a function of carbonate concentration is recommended.

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