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

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Abstract

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.

Details

Original languageEnglish
Title of host publicationProceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)
PublisherANS - American Nuclear Society
Pages903-912
Number of pages10
Edition2022
Publication statusPublished - 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, United States
Duration: 15 May 202220 May 2022

Conference

Conference2022 - PHYSOR - International Conference on Physics of Reactors
Country/TerritoryUnited States
CityPittsburgh, PA
Period2022-05-152022-05-20

Keywords

  • Spent nuclear fuel, Nuclear data, Uncertainty analysis, SANDY, Serpent

ID: 7748090