IAEA-TECDOC-1647_ Review of the Characterisation of Nuclear Graphites in UK Reactors Scheduled for Decommissioning

    Research output: Book/ReportCommissioned report

    Abstract

    Radioactive graphite constitutes a major waste stream which arises during the decommissioning of certain types of nuclear installations. Worldwide, a total of around 250 000 tonnes of radioactive graphite, comprising graphite moderators and reflectors, will require management solutions in the coming years. 14 C is the radionuclide of greatest concern in nuclear graphite; it arises principally through the interaction of reactor neutrons with nitrogen, which is present in graphite as an impurity or in the reactor coolant or cover gas. 3 H is created by the reactions of neutrons with 6 Li impurities in graphite as well as in fission of the fuel. 36 Cl is generated in the neutron activation of chlorine impurities in graphite. Problems in the radioactive waste management of graphite arise mainly because of the large volumes requiring disposal, the long half-lives of the main radionuclides involved and the specific properties of graphite such as stored Wigner energy, graphite dust explosibility and the potential for radioactive gases to be released.
    Original languageEnglish
    PublisherInternational Atomic Energy Agency
    ISBN (Print)978-92-0-106
    Publication statusPublished - Jul 2010

    Publication series

    NameIAEA-TECDOC-1647_ Review of the Characterisation of Nuclear Graphites in UK Reactors Scheduled for Decommissioning
    PublisherIAEA

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