Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
6760204 | Nuclear Engineering and Design | 2016 | 10 Pages |
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.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
R. Gencheva, A. Stefanova, P. Groudev, B. Chatterjee, D. Mukhopadhyay,