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Influence of Temperature on the Corrosion of Uranium Dioxide Nuclear Fuel

Published online by Cambridge University Press:  19 October 2011

Michael E. Broczkowski ,
Jamie J. Noel  and
David W. Shoesmith
Michael E. Broczkowski
Affiliation:
mbroczko@uwo.ca, The University of Western Ontario, Chemistry, 1151 Richmond St., London, N6A 5B7, Canada, 519-661-2111 ex 86357, 519-661-3022
Jamie J. Noel
Affiliation:
jjnoel@uwo.ca, The University of Western Ontario, Chemistry, 1151 Richmond St., London, N6A 5B7, Canada
David W. Shoesmith
Affiliation:
dwshoesm@uwo.ca, The University of Western Ontario, Chemistry, 1151 Richmond St., London, N6A 5B7, Canada
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Abstract

The anodic dissolution of UO2 has been studied at 60°C and the results compared to previous observations at 22°C. The rate of oxidation / dissolution was determined electrochemically at constant potentials in the range -500 mV to 500 mV (vs. SCE). The composition of the electrochemically oxidized surface was determined by X-Ray Photoelectron Spectroscopy (XPS). The onset of oxidation (UO2 → UO2+x) occurred at approximately the same potential (-400 mV) at both temperatures. However, the conversion of UV to UVI, and hence to soluble UO22+, was accelerated by temperature. This acceleration of dissolution caused the development of acidity at localized sites on the fuel surface at lower (less oxidizing) potentials (≥ 100 mV) at 60°C than at 22°C (≥ 350 mV).

Keywords

waste managementx-ray photoelectron spectroscopy (XPS)surface chemistry
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN01-11
Copyright
Copyright © Materials Research Society 2007

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References

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