Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms

A.W. Harris, A. Atkinson, Peter A. Claisse

    Research output: Book/ReportOther report

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    Abstract

    The performance of the cementitious materials within a radioactive waste repository as a physical barrier to the migration of radionuclides depends on the maintenance of the integrity of the barrier. Potentially, this can be compromised by physical damage to the barrier caused by pressurization as gas is generated within the repository. The maintenance of chemical homogeneity within the material used for backfilling the repository may also be compromised as a consequence of gas pressurization through the formation of additional cracks and the reaction of cementitious materials with gases such as carbon dioxide. Consequently, the migration of gas within repository construction materials may be a significant parameter in both the design of a repository and the provision of a safety-case for disposal. The migration of hydrogen, helium, methane, argon and carbon dioxide has been studied for materials selected to be typical of repository structural concretes and grouts that are being considered for backfilling and waste encapsulation. The apparent permeability of these materials to gas has been shown to be dependent on gas type and average pressure in the structural concrete due to the effects of Knudsen flow at pressures of the order of 100 kPa. This is not observed in the grouts due to significantly greater pore size. The permeability coefficients of the grouts are several orders of magnitude greater than those of the concrete. Gas migration is strongly influenced by the degree of water saturation of the materials. The presence of interfaces within the materials results in an increase in permeability at higher degrees of water saturation. A simple model has been developed to simulate the effects of gas pressurization. The tangential hoop stress at the surface of a void is calculated and comparison with the expected tensile strength of the materials is used to assess the potential for cracking. The backfill grouts seem to have sufficient permeability to disperse gas without crack formation.
    Original languageEnglish
    Place of PublicationBrussels
    PublisherCommission of the European Communities
    ISBN (Print)9282652400
    Publication statusPublished - 1993

    Publication series

    NameNuclear Science and Technology
    PublisherCommission of the European Communities
    ISSN (Electronic)1018-5593

    Fingerprint

    radioactive wastes
    gases
    permeability
    dioxides
    maintenance
    carbon dioxide
    saturation
    hoops
    Knudsen flow
    crack initiation
    disposal
    radioactive isotopes
    integrity
    tensile strength
    water
    homogeneity
    voids
    safety
    methane
    cracks

    Bibliographical note

    © ECSC-EEC-EAEC, Brussels, 1993. Source: EU Bookshop, http://bookshop.europa.eu/

    Keywords

    • gas migration
    • radioactive waste
    • cement
    • concrete

    Cite this

    Harris, A. W., Atkinson, A., & Claisse, P. A. (1993). Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms. (Nuclear Science and Technology). Brussels: Commission of the European Communities.

    Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms. / Harris, A.W.; Atkinson, A.; Claisse, Peter A.

    Brussels : Commission of the European Communities, 1993. (Nuclear Science and Technology).

    Research output: Book/ReportOther report

    Harris, AW, Atkinson, A & Claisse, PA 1993, Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms. Nuclear Science and Technology, Commission of the European Communities, Brussels.
    Harris AW, Atkinson A, Claisse PA. Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms. Brussels: Commission of the European Communities, 1993. (Nuclear Science and Technology).
    Harris, A.W. ; Atkinson, A. ; Claisse, Peter A. / Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms. Brussels : Commission of the European Communities, 1993. (Nuclear Science and Technology).
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