Waste management analysis for the nuclear fuel cycle: actinide recovery from combustible waste, October 1977-March 1978

Abstract
Evaluation of the Ce(IV)-NHO/sub 3/ system for recovery of actinides from incinerator ash is continuing. High-fired americium-traced plutonium oxide was completely solubilized in this system and recovery of actinides from incinerator ash was greater than or equal to 95%. Recovery of solubilized plutonium was done by solvent extraction using tributyl phosphate. Tervalent actinides will be recovered by a bidentate organophosphorus solvent extractant. The Ce(IV)-HNO/sub 3/ system was compared with the F/sup -/-HNO/sub 3/ system now in common use. Advantages of the former include less equipment corrosion, no volatilization of silica, and better recovery of actinide in the initial contact. However, additional contacts do not significantly improve recovery (because silica is not solubilized), and the system requires a large liquid/solid ratio for efficient actinide recovery.

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