Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample

Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Augusto Hernandez Solis

    Research outputpeer-review


    The impact of nuclear data cross section uncertainties and covariance matrices on the nuclide vector of spent nuclear fuel was investigated. This exercise was carried out for the Calvert Cliffs fuel assembly D047 benchmark available in the SFCOMPO database. Sample P irradiated in rod MKP109 for four cycles up to a burnup of approximately 44 GWd/MTU was selected for the analysis. Nuclear data uncertainties were taken from the most recent libraries released by evaluation projects JEFF, ENDF/B and JENDL, and were propagated using the SANDY code via a stochastic sampling approach. This paper provides a quantification of the uncertainty on the concentration of several actinides and fission products relevant for spent fuel management. A comparison of the uncertainty predictions using different nuclear data libraries is also included.
    Original languageEnglish
    Title of host publicationProceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)
    PublisherAmerican Nuclear Society
    Number of pages10
    StatePublished - 23 Jun 2022
    Event2022 - PHYSOR - International Conference on Physics of Reactors: Making Virtual a Reality: Advancements in Reactor Physics to Leap Forward Reactor Operation and Deployment - Sheraton Pittsburgh Hotel, Pittsburgh, PA
    Duration: 15 May 202220 May 2022


    Conference2022 - PHYSOR - International Conference on Physics of Reactors
    Country/TerritoryUnited States
    CityPittsburgh, PA

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