Federico Grimaldi
Nuclear data uncertainty quantification in fuel depletion calculations.
Rel. Sandra Dulla. Politecnico di Torino, Corso di laurea magistrale in Ingegneria Energetica E Nucleare, 2022
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Abstract
Spent nuclear fuel characterisation is a topic of major interest in these times of change, when sustainable energy scenarios are shaped. The burden of experimental assessment of spent fuel inventory is too large to allow the application of these techniques to all the fuel used in nuclear reactors. For this reason, fuel assembly models capable of predicting the discharged fuel inventory are needed. The validation of such models and of the capabilities of the codes used is often assessed through benchmark modelling. This consists in models of specific fuel assemblies designed following given specifications, which allows for comparison of the model prediction with the results of the experimental campaigns performed on samples from those assemblies, but also for comparison of different modelling codes and of nuclear data libraries.
When it comes to uncertainty propagation, several uncertainty sources should be considered
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