ISSN:
1588-2780
Source:
Springer Online Journal Archives 1860-2000
Topics:
Chemistry and Pharmacology
,
Energy, Environment Protection, Nuclear Power Engineering
Notes:
Abstract These studies are an extension of carlier work on the recovery of actinides extracted by Truex solvent from simulated high level waste solution, with a mixture of weak acid, weak base and complexing agent used as a strippant. The effectiveness of the proposed strippant, consisting of formic acid, hydrazine hydrate and citric acid, is tested in a counter-current mode using mixer-settler in the present studies. The studies show that near quantitative recovery of americium and plutonium is feasible from acid-bearing Truex solvent with no reflux (reextration) of activity. Use of this strippant reduces considerably the generation of secondary waste.
Type of Medium:
Electronic Resource
URL:
http://dx.doi.org/10.1007/BF02349844
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