Original scientific paper

NPP KRŠKO CONTAINMENT MODELLING WITH THE ASTEC CODE

SINIŠA ŠADEK orcid.org/0000-0002-4707-0087 ; University of Zagreb Faculty of Electrical Engineering and Computing
DAVOR GRGIĆ ; University of Zagreb Faculty of Electrical Engineering and Computing

Abstract

ASTEC is an integral computer code jointly developed by Institut de
Radioprotection et de Sûreté Nucléaire (IRSN, France) and Gesellschaft für Anlagenund
Reaktorsicherheit (GRS, Germany) to assess nuclear power plant behaviour
during a severe accident (SA). The ASTEC code was used to model and to simulate
NPP behaviour during a postulated station blackout accident in the NPP Krško.
The accident analysis was focused on containment behaviour; however the complete
integral NPP analysis was carried out in order to provide correct boundary
conditions for the containment calculation. During the accident, the containment
integrity was challenged by release of reactor system coolant through degraded
coolant pump seals, molten corium concrete interaction and direct containment
heating mechanisms. Impact of those processes on relevant containment
parameters, such as compartments pressures and temperatures, is going to be
discussed in the paper.

Keywords

ASTEC; core melt; direct containment heating; molten corium concrete interaction; PWR

Hrčak ID:

199282

URI

https://hrcak.srce.hr/199282

Publication date:

15.9.2017.

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