Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

Nuclear safety relies to a good extent on thoroughly validated codes. However, code predictions are affected by uncertainties that need to be quantified for a more accurate evaluation of safety margins. In this regard, the present paper proposes a preliminary uncertainty and sensitivity analysis of...

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Bibliographic Details
Published in:Energies
Main Authors: Michela Angelucci, Sandro Paci, Francisco Feria, Luis Enrique Herranz
Format: Article
Language:English
Published: MDPI AG 2022-02-01
Subjects:
dry cask
spent fuel
uncertainty
MELCOR
nuclear safety
Online Access:https://www.mdpi.com/1996-1073/15/3/1216

Internet

https://www.mdpi.com/1996-1073/15/3/1216

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