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Report No.

Development of electrochemical reduction process for oxide nuclear fuel, 9; Solubility measurement of Pu$$_{2}$$O$$_{3}$$ in molten LiCl-Li$$_{2}$$O

Kato, Tetsuya*; Sakamura, Yoshiharu*; Iwai, Takashi; Arai, Yasuo

In order to apply the pyrometallurgical reprocessing to spent oxide fuels, reduction techniques of oxide in molten salt have been studied. In the previous reduction experiments, a small amount of Pu has been found to move out of the reduced fuel and dissolve into molten LiCl-Li$$_{2}$$O. In this study, solubility of Pu in molten LiCl-Li$$_{2}$$O was measured to obtain quantitative data for the Pu dissolution. The Pu solubility in the molten LiCl-Li$$_{2}$$O containing Pu$$_{2}$$O$$_{3}$$ precipitates increased with increasing Li$$_{2}$$O concentration in the molten salt to be approximately 0.3wt%Pu at 8wt%Li$$_{2}$$O and 923 K.



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