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Xps and Sem Studies on the Corrosion of UO2 Cointaining Plutonium in Demineralized and Carbonated Water.

Published online by Cambridge University Press:  11 February 2011

J. Cobos ,
T. Wiss ,
T. Gouder  and
V. V. Rondinella
J. Cobos
Affiliation:
European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach, 2340, 76125 Karlsruhe, Germany.
T. Wiss
Affiliation:
CIEMAT, Avda Complutense 22, E-28040 Madrid, Spain. [email protected]
T. Gouder
Affiliation:
CIEMAT, Avda Complutense 22, E-28040 Madrid, Spain. [email protected]
V. V. Rondinella
Affiliation:
CIEMAT, Avda Complutense 22, E-28040 Madrid, Spain. [email protected]
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Abstract

An oxidation and dissolution study has been performed on UO2 pellets containing ∼10 and ∼0.1 wt. % 238Pu, ∼10 wt. % 239Pu and on undoped UO2 to investigate the effects of radiolysis and composition on the corrosion behavior of spent fuel. The so-called alpha-doped UO2 is used to simulate the alpha-radiation field of different types of commercial LWR spent fuel after different storage times. Leaching experiments in demineralized and carbonated water at room temperature under oxidizing conditions showed that relatively high amounts of 238Pu were released. The leached surfaces were examined with X-ray Photoemission Spectroscopy (XPS), and the progressive surface oxidation was monitored. The oxidation of the U(IV) during the leaching experiments, in the materials doped with 238Pu resulted in precipitation of U(VI) phases: enhanced formation of studtite for the strongest radiation field and shoepite at low radiation field was observed on the surface of the pellet. Essentially no precipitation of Pu-rich phases was directly observed. Leaching in carbonated water and characterization of UO2 containing 239Pu under the same experimental conditions were performed and the results compared to those for alpha-doped UO2. The chemistry effects due to the presence of Pu in addition to alpha-radiolysis were investigated.

Type
articles
Information
MRS Online Proceedings Library (OPL) , Volume 757: Symposium II – Scientific Basis for Nuclear Waste Management XXVI , 2002 , II9.2
Copyright
Copyright © Materials Research Society 2003

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References

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