Demonstration of U(VI)/Pu(IV) Separation by Solvent Extraction in Modified Lab-Scale Annular Centrifugal Contactors Using D2EHiBA Extractant

The objective of this work is to demonstrate the U(VI)/Pu(IV) separation without the use of complexant or reductant, obtaining a high decontamination factor (DF) for Pu(IV) and Ru(III), using TBP as a benchmark. For this purpose, we have use of lab-scale short residence time annular centrifugal contactors (ACCs). The used methods and results are explained. The U(VI)/Pu(IV) separation in modified lab-scale annular centrifugal contactors using D2EHiBA extractant without the need of using complexants or reductants was successful, and it was demonstrated that this solvent extraction process can be envisioned for selective recovery of uranium from spent enriched uranium solutions