Abstract: In response to the need for safe and sustainable energy solutions, the emergence of Small Modular Reactors (SMRs) has attracted significant interest. SMRs are designed to be safer than traditional Nuclear Power Plants (NPPs) due to their smaller core loads and advanced safety features. The on-going HORIZON-EURATOM SASPAM-SA project addresses the transferability of knowledge from large Light Water Reactors (LWRs) to integral Pressurized Water Reactors (iPWRs) and analyses the behaviour of generic SMR designs with passive mitigation strategies under accident conditions. In this context, this study investigates the safety assessment of a generic natural circulation iPWR using the code ASTEC (Accident Source Term Evaluation Code) developed by the French Institute for Radia-tion Protection and Nuclear Safety (IRSN). The ASTEC code is capable of simulating a complete ac-cident sequence in a NPP, from the initial event to the potential release of radioactive elements out-side the containment, involving the modelling of diverse thermal-hydraulic and physico-chemical phe-nomena. In this work, the results derived from the analysis of hypothetical Design-Basis Accident (DBA) and Severe Accident (SA) scenarios, in one of the two generic iPWRs considered in the SAS-PAM-SA project, are presented, showing the ability of the code to adequately describe the main ther-mal-hydraulic and core degradation phenomena.

Speaker
Herr Dr. Mauricio Exequiel Cazado

Karlsruher Institut für Technologie
Institut für Neutronenphysik und Reaktortechnik, INR

Organizer
Institut für Neutronenphysik und Reaktortechnik, INR
Karlsruher Institut für Technologie
Hermann-von-Helmholtz-Platz 1
76344 Eggenstein-Leopoldshafen
Mail: ingeborg schwartz ∂does-not-exist.kit edu

Targetgroup
Entrepreneur, Everybody, Pupil, Students, Researcher