| 摘要 |
According to the method of the present invention, in the decontamination step, U, Pu and Np contained in the spent nuclear fuel are extracted in the form U(VI), Pu(IV) and Np(VI) by an organic solvent and, in the Np separation step and the U-Pu recovery step, only Np is reduced to valency V in the coexisting U(VI) and Pu(IV) system and it can therefore be separated from U and Pu. In the U/Pu distribution step, Pu(IV) coexisting with U(VI) can be selectively reduced to valency III by isobutyraldehyde in order to be separated.
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