Behaviour of vitrified radioactive waste under simulated repository conditions.

R. De Batist, N. Jacquet-Francillon, F. Lanza, Guenter Malow, J. A.C. Marples

    Research outputpeer-review

    Abstract

    Vitrified radioactive waste products, designed either for the incorporation of high activity fission product wastes from reprocessing plants or for the conditioning of alpha contaminated wastes through slagging incineration, have been tested to investigate their behaviour under simulated repository conditions. Three types of deep geological formation have been considered: rocksalt, hard rock and clay. Both inactive and lightly doped materials were studied. Information has been obtained about the alteration of the waste forms (crystallization, surface layer formation) and about the diffusion of the radionuclides in some of the geological materials.

    Original languageEnglish
    Title of host publicationCommission of the European Communities, (Report) EUR
    PublisherCambridge University Press
    Pages212-231
    Number of pages20
    ISBN (Print)0521325803
    StatePublished - 1986

    Publication series

    NameCommission of the European Communities, (Report) EUR

    ASJC Scopus subject areas

    • General Engineering

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