Article ID Journal Published Year Pages File Type
8068701 Annals of Nuclear Energy 2015 6 Pages PDF
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.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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