| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 4925714 | Nuclear Engineering and Design | 2017 | 17 Pages |
Abstract
3) âAnalysis of external reactor vessel cooling. For this purpose the ASTEC code was used for performing analysis of core degradation scenarios, the ANSYS code for structural analysis of reactor vessel subjected to thermal load from corium, and RELAP5 code for assessment of external reactor vessel cooling. Finally, implementation of IVR system in NPPs in Czech Republic and Slovakia is shortly described.
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Authors
Peter Matejovic, Miroslav Barnak, Milan Bachraty, Lubomir Vranka, Robert Berky,