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Leaching Behaviour of Low -Activity Alpha-Doped UO2.

Published online by Cambridge University Press:  17 March 2011

Vincenzo V. Rondinella ,
Joaquin Cobos  and
Thierry Wiss
Vincenzo V. Rondinella
Affiliation:
European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, 76125 Karlsruhe, Germany, rondinella@itu.fzk.de
Joaquin Cobos
Affiliation:
Previously at CIEMAT, Avda Complutense 22, E-28040 Madrid, Spain
Thierry Wiss
Affiliation:
European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, 76125 Karlsruhe, Germany
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Abstract

So-called alpha-doped UO2 (i.e. UO2 containing short-lived alpha-emitters) can reproduce the activity levels of spent fuel at different ages. Previous experiments showed significant effects of alpha-radiolysis at relatively high alpha-activity levels (e.g., in the range 108 – 1010 Bq/g). This study shows the results of leaching tests done on low alpha-activity material (106 – 107 Bq/g). UO2 containing ∼10 and ∼1 wt. % 233U was leached at room temperature in deionized and carbonated water under deaerated conditions. Higher release in carbonated water was observed. A clear radiolytic enhancement of the concentration of uranium in solution was observed for the material containing 10 wt. % 233U. The dissolved U concentration was very close to the values previously observed for higher activity alpha-doped UO2 and confirmed the finding that under relatively high surface/volume condition the measured amount of U in solution is essentially independent of the alpha-activity level. No significant radiolysis effect was detected for the material doped with 1% 233U compared to undoped UO2 after ∼4 months of leaching. The post- leaching SEM examination revealed no pronounced etching of the surfaces.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC9.8
Copyright
Copyright © Materials Research Society 2004

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