Sensitivity studies on the neutron emission of spent nuclear fuel by means of the origen-ARP code

    Research outputpeer-review


    This paper focuses on the impact of some parameters of the irradiation history on the total neutron emission of a SFE. The tool used to determine the neutron emission was the ORIGEN-ARP code. The cases considered a Low Enriched Uranium (LEU) 17×17 PWR fuel with an initial enrichment of 4.5%. The burnup ranged between 5 and 70 GWd/tU and 30 values of cooling time, from 0 up to 3 million years, were considered. The parameters that were varied were the average power level, the cooling time between cycles and the duration of the irradiation cycle. The obtained neutron emission values are presented and discussed. Conclusions on the role of the considered irradiation history parameters on the total neutron emission and on the impact of the main neutron emitters are drawn.
    Original languageEnglish
    Title of host publicationINMM 55th Annual Meeting Proceedings
    Place of PublicationAtlanta, United States
    PublisherINMM - Institute of Nuclear Materials Management
    Number of pages8
    ISBN (Print)9781634396219
    StatePublished - 24 Jul 2014
    Event2014 - INMM : 55th Annual Meeting of the Institute of Nuclear Materials Management - INMM - Institute of Nuclear Materials Management, Atlanta, Georgia
    Duration: 20 Jul 201424 Jul 2014
    Conference number: INMM 2014


    Conference2014 - INMM
    Country/TerritoryUnited States
    CityAtlanta, Georgia

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