Diffusion of uranium in compacted sodium bentonite

Arto Muurinen, Kaija Ollila, Jarmo Lehikoinen

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

    Abstract

    In this study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The parameters varied in the study were the density of bentonite, the salt content of the solution and the redox conditions. In the studies with non-saline water of total dissolved solids about 300 ppm, uranium was both in aerobic and anaerobic experiments as anionic complexes and followed the anionic diffusion mechanism. Anion exclusion decreased effective diffusion coefficients, especially in more dense samples. In the studies with saline water of total dissolves solids about 35000 ppm, uranium appeared in the aerobic experiments probably as cationic complexes and followed the cationic diffusion mechanism. Uranium in the saline, anaerobic experiment was probably U(OH)4 and followed the diffusion mechanism of neutral species.
    Original languageEnglish
    Title of host publicationScientific Basis for Nuclear Waste Management XVI
    Subtitle of host publicationSymposium V
    EditorsC.G. Interrante, R.T. Pabalan
    Place of PublicationPittsburgh
    PublisherMaterials Research Society
    Pages409-416
    ISBN (Print)978-1-558-99189-7
    DOIs
    Publication statusPublished - 1993
    MoE publication typeA4 Article in a conference publication
    EventMaterials Research Society Fall Meeting 1992 - Boston, United States
    Duration: 30 Nov 19924 Dec 1992

    Publication series

    SeriesMaterials Research Society Symposia Proceedings
    Volume294
    ISSN0272-9172

    Conference

    ConferenceMaterials Research Society Fall Meeting 1992
    CountryUnited States
    CityBoston
    Period30/11/924/12/92

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  • Cite this

    Muurinen, A., Ollila, K., & Lehikoinen, J. (1993). Diffusion of uranium in compacted sodium bentonite. In C. G. Interrante, & R. T. Pabalan (Eds.), Scientific Basis for Nuclear Waste Management XVI: Symposium V (pp. 409-416). Materials Research Society. Materials Research Society Symposia Proceedings, Vol.. 294 https://doi.org/10.1557/PROC-294-409