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The aim of this work is to study the dissolution rates of unirradiated UO(2) as a function of hydrogen concentration, and to use the acquired experience to extend this study to the dissolution mechanisms of the spent fuel and to the release of radionuclides during leaching. For the determination of the dissolution rate, a dynamic leaching set-up was used under oxidizing conditions for two months and at room temperature. The dissolution rate is determined following the methods used for the analysis of mixed flow reactors.

Additional information

Bibliographic Reference: Paper presented: 25th Annual Conference, Granada (ES), 17-19th November (1999)
Availability: Available from Public Relations and Publications Unit, Ispra (IT)
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