Adoption of in-vessel retention concept for VVER-440/V213 reactors in Central European Countries

3) ∗Analysis 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.