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*

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.

Language	:	Japanese
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Meeting title	:	日本原子力学会2016年秋の大会
Held date	:	2016/09
Location (city)	:	久留米
Location (country)	:	日本
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Keywords	:	使用済燃料; 直接処分; 二酸化ウラン; 溶解速度; 炭酸濃度影響; 酸化還元状態
Research Facility	:	ENTRY(地層処分基盤研究施設)
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Registration No. : BB20160430
JAEA Abstracts No. :
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Estimation of source term for spent fuel disposal, 2; Effect of carbonate concentration on dissolution rate of UO and spent fuel; A Review

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