0586310 - ÚT 2025 SE eng C - Conference Paper (international conference)
Gál, P. - Kotouč, M. - Dymáček, Petr - Gabriel, Dušan - Masák, Jan
Reactor pressure vessel integrity during severe accident with core meltdown: characterization of material parameters, structure integrity assessment and thermal-hydraulic assessment.
Proceedings of the 11th European Review Meeting on Severe Accidents Research (ERMSAR2024). Stockholm: Königlich Technische Hochschule Stockholm (KTH), 2024 - (Gabrielli, F.; Herranz, L.; Paci, S.)
[The 11th European Review Meeting on Severe Accident Research (ERMSAR2024). Stockholm (SE), 13.05.2024-16.05.2024]
R&D Projects: GA TA ČR TITSSUJB938
Institutional support: RVO:61388998 ; RVO:68081723
Keywords : IVMR * FEM * RPV integrity * TH calculations * creep * ablation
OECD category: Nuclear related engineering; Materials engineering (UFM-A)
Result website:
https://publikationen.bibliothek.kit.edu/1000174165/v2

For high power reactors, such as VVER 1000, is the assessment of reactor pressure vessel (RPV) during several accident (SA) with application of In-Vessel Melt Retention (IVMR) still an open issue. There is no international consensus or document that defines the exact procedure how to assess the RPV during SA as in “conventional” assessment such as fatigue. This paper is focused on the basic steps of RPV assessment and how to compute deformations on RPV wall. This paper describes material inputs, severe accident progression calculations to obtain thermal boundary conditions and finally the structural assessment of RPV for the reference plant being Czech Temelin nuclear power plant (NPP), equipped with 2 VVER-1000/320 units.
Permanent Link: https://hdl.handle.net/11104/0361520