Impact of the ENDF/B-VI cross sections on the RPV fluence determination

    Research output: Contribution to journalConference articlepeer-review

    Abstract

    The calculations with the broad-group cross-section library Bugle-96, and atom displacement (dpa) cross sections for iron, both derived from ENDF/B-VI data, result in higher calculated fast neutron fluxes, better agreement of calculations with radiometric dosimeter measurements, and significantly slower dpa rate attenuation through pressure vessel walls relative to the results with their predecessors: the Sailor library and ASTM iron dpa cross sections.

    Original languageEnglish
    Pages (from-to)124-131
    Number of pages8
    JournalASTM Special Technical Publication
    Issue number1398
    DOIs
    StatePublished - 2001
    EventReactor Dosimetry: Radiation Metrology and Assesment - Osaka, Japan
    Duration: Sep 12 1999Sep 17 1999

    Keywords

    • Dosimetry
    • ENDF/B-VI
    • Neutron transport
    • Reactor pressure vessel

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