VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor

Within the framework of the French 4th-generation Sodium-cooled Fast Reactor safety assessment, methodology on VVUQ (Verification, Validation, Uncertainty Quantification) is conducted to demonstrate that the CEA's thermal-hydraulic Scientific Computation Tools (SCTs) are effective and operation...

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Bibliographic Details

Published in:	EPJ Nuclear Sciences & Technologies
Main Authors:	Marie Nathalie, Li Simon, Marrel Amandine, Marquès Michel, Bajard Sophie, Tosello Annick, Perez Jorge, Grosjean Baptiste, Gerschenfeld Antoine, Anderhuber Marine, Geffray Chotaire, Gorsse Yannick, Mauger Gédéon, Matteo Laura
Format:	Article
Language:	English
Published:	EDP Sciences 2021-01-01
Online Access:	https://www.epj-n.org/articles/epjn/full_html/2021/01/epjn200008/epjn200008.html