You are here

ASTEC − Accident Source Term Evaluation Code

Printer-friendly version

The ASTEC code (Accident Source Term Evaluation Code), jointly developed since several years by the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the German Gesellschaft für Anlagen und Reaktorsicherheit mbH (GRS), aims at simulating an entire Severe Accident (SA) sequence in a nuclear water-cooled reactor from the initiating event through the release of radioactive elements out of the containment.

ASTECThe main ASTEC applications are therefore source term determination studies, level 2 Probabilistic Safety Assessment (PSA 2) studies including the determination of uncertainties, accident management studies and physical analyses of experiments to improve the understanding of the phenomenology.