Extension of the SCK•CEN spent fuel inventory library

Alessandro Borella, Mario Cometto, Riccardo Rossa, Klaas van der Meer, Romolo Remetti

    Research outputpeer-review


    SCK•CEN is performing R&D work related to the development of Non Destructive Assay on spent fuel elements. Due to difficulty in accessing spent fuel, having an accurate and validated model of the measurement equipment and a characterization of the source term is important for this type of studies. To better understand and develop methods based on neutron counting and gamma spectroscopy, a significant effort was done to determine the source terms associated to spent fuel with depletion and evolution code calculations. This paper reports about the extension of the SCK•CEN spent fuel inventory library with the ORIGEN-ARP code. The cases considered a Low Enriched Uranium 17×17 PWR fuel with an initial enrichment of 2.0, 2.5 and 3.0 %. This set of enrichments complements the data published previously for enrichments between 3.5 % and 5 %. In addition, results obtained with Mixed Oxide (MOX) fuel are presented and discussed. The impact of the initial enrichment, for LEU fuel, and the Pu mass, for MOX fuel, on the neutron emission and production of the main neutron emitters, are also studied.
    Original languageEnglish
    Title of host publicationESARDA 37th Annual Meeting Proceedings
    Place of PublicationLuxembourg
    StatePublished - 6 Aug 2015
    Event2015 - ESARDA - European Safeguards Research & Development Association: 37th ESARDA Annual Meeting - Midland Hotel, Manchester
    Duration: 19 May 201521 May 2015


    Conference2015 - ESARDA - European Safeguards Research & Development Association
    Country/TerritoryUnited Kingdom
    Internet address

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