Sensitivity and uncertainty analysis of PWR spent fuel observables to operational and model parameters

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review


  • FANC-AFCN - Federaal agentschap voor nucleaire controle-Agence fédérale de contrôle nucléaire
  • JSI - Jozef Stefan Institute
  • EC - JRC - European Commission - Joint Research Centre

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Sensitivity and uncertainty analyses of spent nuclear fuel observables - decay heat, neutron and ..--rayray emission rate - to operational and model parameters have been performed. A 2D model representing a typical PWR 17 × 17 UO2 fuel assembly has been taken as reference. The Serpent code and ENDF/B-VII.1 evaluated nuclear data library have been used for the analyses. Relative uncertainty of decay heat, neutron and .-ray emission rates due to MC counting statistics, as well as the number of fuel pin radial regions required for an accurate characterization of SNF neutron emission, have been estimated. A parametric study has been carried out to investigate the impact of the homogenization to an average value of the fuel and moderator temperature, boron concentration power and burnup on the prediction of the selected observables. In addition, linear sensitivity coefficients have been calculated.


Original languageEnglish
Title of host publicationProceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)
PublisherANS - American Nuclear Society
Number of pages10
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


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


  • Sensitivity, Uncertainty, Spent nuclear fuel

ID: 7748075