Computer modelling of radioactive source terms at a tokamak reactor

A. Meide

    Research output: Book/ReportReportResearch

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    Abstract

    The Monte Carlo code MCNP has been used to create a simple three-dimensional mathematical model representing 1/12 of a tokamak fusion reactor for studies of the exposure rate level from neutrons as well as gamma rays from the activated
    materials, and for later estimates of the consequences to the environment, public, and operating personnel. The model is based on the recommendations from the NET/INTOR workshops.
    Original languageEnglish
    Place of PublicationRoskilde, Denmark
    PublisherRisø National Laboratory
    Number of pages10
    ISBN (Print)87-550-1077-6
    Publication statusPublished - 1984
    SeriesRisø-M
    Number2482
    ISSN0418-6435

    Keywords

    • Risø-M-2482
    • M codes
    • Mathematical models
    • Monte Carlo method
    • Neutron transport
    • Tokamak devices
    • Three-dimensional calculations

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