Abstract: Mixed radioactive wastes, such as those that include a radioactive component and a dissolved salt component, are treated by directing the waste through at least one ion-exchange medium that binds at least a portion of the radioactive component. A liquid discharge stream from which the radioactive component has been separated, and which includes the dissolved salt component, is directed into a molten bath that causes at least a portion of at least one dissolved salt component of the liquid discharge stream to be reductively vaporized and thereby form at least one vaporized product. A gaseous discharge stream is generated by the molten bath that includes at least one vaporized product. In one specific embodiment, the mixed radioactive waste includes radioactive cesium as the radioactive component and sodium nitrate as the dissolved salt component.

Abstract: A Pu(IV) polymer not extractable from a nuclear fuel reclaiming solution by conventional processes is electrolytically converted to Pu.sup.3+ and PuO.sub.2.sup.2+ ions which are subsequently converted to Pu.sup.4+ ions extractable by the conventional processes.

Abstract: The rate of reduction of Pu(IV) to Pu(III) in nitric acid solution containing a reducing agent is enhanced by exposing the solution to 200-500 nm electromagnetic radiation. Pu values are recovered from an organic extractant solution containing Pu(IV) values and U(VI) values by the method of contacting the extractant solution with an aqueous nitric acid solution in the presence of a reducing agent and exposing the aqueous solution to electromagnetic radiation having a wavelength of 200-500 nm. Under these conditions, Pu values preferentially distribute to the aqueous phase and U values preferentially distribute to the organic phase.