Measurement of dissolution rates of UO2 matrix with the isotope dilution method

Kaija Ollila, V. Oversby

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    1 Citation (Scopus)


    The objective of this work was to measure the actual rates of matrix dissolution of UO2 in synthetic groundwater by using an isotope dilution method to provide a quantitative estimate of precipitation effects. A preliminary series of tests was performed under oxidising conditions, in contact with air. The second series of tests was under reducing conditions produced by actively corroding iron. The solid phases were fragments of unirradiated fuel pellets and intact pellets. The aqueous phase was a dilute, synthetic groundwater - so-called modified Allard water that is buffered by sodium bicarbonate/carbonate. This paper gives results for the experiments under oxidising conditions and preliminary tests under reducing conditions. In contact with air, the U concentrations reached higher levels than measured in previous experiments with spent fuel or with UO2 pellets. The comparison of the U concentrations calculated from isotopicratios with the experimental results suggests precipitation has begun at later stages of restarted tests. The measurements in the presence of actively corroding iron gave very low concentrations in the aqueous phase. At contact times longer than one week, all U seemed to disappear from solution and sorb or precipitate on UO2 or Fe surfaces in the test vessel.
    Original languageEnglish
    Title of host publicationScientific Basis for Nuclear Waste Management XXVII
    EditorsV.M. Oversby, L.O. Werme
    PublisherMaterials Research Society
    ISBN (Print)1-55899-752-0, 978-1-55899-752-3
    Publication statusPublished - 2004
    MoE publication typeA4 Article in a conference publication
    Event27th MRS Symposium on the Scientific Basis for Nuclear Waste Management - Kalmar, Sweden
    Duration: 15 Jun 200319 Jun 2003

    Publication series

    SeriesMRS Online Proceedings


    Conference27th MRS Symposium on the Scientific Basis for Nuclear Waste Management


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