A Summary of the Uncertainty and Sensitivity Analysis of a Generic CANDU 6 Plant by Means of Severe Accident Codes in the Framework of the IAEA CRP I31033
S.M. Petoukhov, A.C. Morreale (CNL)
Proceedings | 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-14) | Vancouver, British Columbia, Canada, August 25–28, 2024 | Pages 1587-1600