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...
Main Authors: | , , , , , , , , , , , , , |
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Format: | Article |
Language: | English |
Published: |
EDP Sciences
2021-01-01
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Series: | EPJ Nuclear Sciences & Technologies |
Online Access: | https://www.epj-n.org/articles/epjn/full_html/2021/01/epjn200008/epjn200008.html |