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Analysis of isotopic assay data from the MALIBU program

    Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

    7 Scopus citations

    Abstract

    Acquisition and analysis of experimental isotopic assay data are essential for validating computer code predictions of isotopic composition for spent nuclear fuel in order to establish the uncertainty and bias associated with code predictions. Recently available experimental data for uranium oxide spent fuel, acquired through the MALIBU international program, are analyzed in this paper. The analyzed measurements include extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Analysis of the measurements was performed using the two-dimensional depletion module TRITON in the SCALE computer code system.

    Original languageEnglish
    Title of host publicationInternational Conference on the Physics of Reactors 2008, PHYSOR 08
    PublisherPaul Scherrer Institut
    Pages1744-1750
    Number of pages7
    ISBN (Print)9781617821219
    StatePublished - 2008
    EventInternational Conference on the Physics of Reactors 2008, PHYSOR 08 - Interlaken, Switzerland
    Duration: Sep 14 2008Sep 19 2008

    Publication series

    NameInternational Conference on the Physics of Reactors 2008, PHYSOR 08
    Volume3

    Conference

    ConferenceInternational Conference on the Physics of Reactors 2008, PHYSOR 08
    Country/TerritorySwitzerland
    CityInterlaken
    Period09/14/0809/19/08

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