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Waste management analysis for the nuclear fuel cycle. I. Actinide recovery from aqueous salt wastes
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.
Date:
May 12, 1979
Creator:
Martella, L.L. & Navratil, J.D.
System:
The UNT Digital Library