Computer modelling of radioactive source terms at a tokamak reactor

A. Meide

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    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


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


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