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Actinide Speciation in Spent Fuel Leaching Studies

Published online by Cambridge University Press:  21 February 2011

Gregory R. Choppin
Gregory R. Choppin*
Affiliation:
Department of Chemistry, Florida State University, Tallahassee, Florida 32306
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Abstract

The uranium and plutonium chemistry relevant for spent fuel leach studies is discussed. Model calculations are evaluated by comparison with the results of spent UO2 fuel leaching obtained in the Swedish SKB program. The thermodynamic data were found to agree sufficiently with the measured solution concentrations that it can be assumed that in oxic natural waters, leachate uranium from spent fuel would be uranyl carbonate complexes in the solution (or hydroxo complexes in the absence of carbonate) while schoepite would be the solubility limiting solid. For plutonium, PuO2 + would be the solution species and Pu(OH)4 the solubility limiting solid.

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Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 449
Copyright
Copyright © Materials Research Society 1990

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References

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