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At least 127 records · Page 7
All sourcesNASA NTRSDOE OSTI
DOE OSTI2024

Process Intensification for Recovery of Uranium from Spent Fuel Using DEHiBA

Two approaches are being pursued to intensify the DEHiBA process for recovery of U from used nuclear fuel. For the traditional solvent extraction approach in which the fuel is first dissolved in hot nitric acid, the DEHiBA concentration was adjusted to 1.5 M. This allows for increased loading in the organic phase, but the organic phase U concentration should remain below 100 g/L to avoid unfavorable physicochemical properties that would upset the hydrodynamics in contacting equipment such as centrifugal contactors. Direct extraction of U into the 1.5 M DHEiBA solvent is another intriguing approach to intensifying the process. In this case, the hot nitric acid dissolution step is avoided, a potential significant simplification of the process. Strategies for routing Tc, Np, and Pu to the HLW stream will likely need to be developed to avoid contamination of the U product with these undesirable species.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗