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Thesis
Home   /   Thesis   /   Assessment of a new model for the investigation of an hypothetical Steam Generator Tube Rupture (SGTR) accident in Lead-cooled Fast Reactors (LFR).

Assessment of a new model for the investigation of an hypothetical Steam Generator Tube Rupture (SGTR) accident in Lead-cooled Fast Reactors (LFR).

Engineering sciences Mathematics - Numerical analysis - Simulation Mechanics, energetics, process engineering

Abstract

The purpose of this PhD thesis is to implement and assess a new vapor explosion model in the
CEA code Europlexus, to investigate an hypothetical steam generator tube ruptures (SGTR) inside
the primary coolant pool of a lead-cooled fast reactors (LFR).

Laboratory

Département de Modélisation des Systèmes et Structures
Service d’Etudes Mécaniques et Thermiques
Laboratoire d’études de DYNamique
IP. Paris
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