Waste Management Analysis for the Nuclear Fuel Cycle. I. Actinide Recovery from Aqueous Salt Wastes.

摘要

A preliminary feasibility study of solvent extraction methods has been completed for removing actinides from selected salt wastes likely to be produced during reactor fuel fabrication and reprocessing. The use of a two-step solvent extraction system,tributyl phosphate (TBP) followed by a bidentate organophosphorus extractant (DHDECMP),appears most efficient for removing actinides from salt waste. The TBP step would remove most of the plutonium and >99.99% of the uranium. The second step,using DHDECMP,would remove >99.91% of the americium,the remaining plutonium (>99.98%),and other actinides from the acidified salt waste. (ERA citation 04:042409)