Article ID Journal Published Year Pages File Type
6760204 Nuclear Engineering and Design 2016 10 Pages PDF
Abstract
The results from four calculations have been assessed: two integral calculations made with ASTECv2.0r3with and without simulation of external vessel water cooling and two stand-alone calculations made with the ICARE module of ASTECv2.0r3. The heat fluxes from the corium to the vessel and the heat fluxes from the vessel to the outside water have been predicted by the code. There were also accounted periods of maximum heat input from the corium to the vessel steel wall.
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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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