Abstract
Uncertainty propagation and quantification, when applied to the field of nuclear fuel cycle scenario studies,
usually only considers a set of easily quantifiable input parameters, leaving out the effects of the
modelling approaches. In order to extend the validity of these analyses, two different codes, ANICCA
and TR_EVOL (developed respectively by SCKCEN and CIEMAT), have been benchmarked through a study
of an advanced and realistic nuclear fuel cycle scenario with the aim of assessing the impact of the use of
different tools in the fuel cycle scenario uncertainty quantification. Additionally, a classical uncertainty
propagation analysis was done following the total Monte Carlo and sensitivity approaches in order to
compare the system uncertainties with the dissimilarities due the simulators. Results shows that the
impact of the fuel cycle simulators cannot be neglected for certain observables, and that their effects
become relevant as the scenarios extends over time due their cumulative effect.
Details
Original language | English |
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Article number | 107160 |
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Pages (from-to) | 1-9 |
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Number of pages | 9 |
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Journal | Annals of nuclear energy |
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Volume | 137 |
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DOIs | |
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Publication status | Published - 30 Oct 2019 |
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