Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8068701 | Annals of Nuclear Energy | 2015 | 6 Pages |
Abstract
ICARE/ASTECv2.0r3 computer code was used to predict the heat fluxes from the corium to the vessel and the heat fluxes from the vessel to the outside coolant. It highlighted key periods of maximum heat input to the vessel steel wall that the steel wall has to be capable of sustaining.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
R. Gencheva, A. Stefanova, P. Groudev,