Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections

Hans Hvidtfeldt Larsen

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    Abstract

    Three-dimensional overall calculations are set up with the SYNTRON/VOID program as whole core calculations on the Dresden 1 reactor. The utility of the methods used for the production of box average cross sections on the basis of separate fuel box calculations with the CDB code are investigated. An alternative method for the determination of box average diffusion constants is proposed.
    Original languageEnglish
    Place of PublicationRoskilde, Denmark
    PublisherRisø National Laboratory
    Number of pages17
    Publication statusPublished - 1973
    SeriesRisø-M
    Number1616
    ISSN0418-6435

    Keywords

    • Risø-M-1616

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