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Report No.
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MOX reprocessing at TRP, 6; Study of solvent degradation

Hoshi, Takahiro; Kawaguchi, Yoshihito; Kitao, Takahiko ; Oyama, Koichi ; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

For reprocessing nuclear spent fuel, in future, used for plutonium-thermal and fast-breeding reactor, density of DBP in extraction solvent on reprocessing Fugen MOX Type B fuel was measured. And we formulated an equation for increased density of DBP to estimate density of DBP in extraction cycle.

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