C2 : Ageing of the structural components in the nuclear power plant

Informations générales

Objectif(s)

Macroscopic consequences of irradiation damage in terms of mechanical properties (hardening and embritlement), dimensional stability (growth and swelling) and environmental resistance.

Physical based models in relation with microstructural evolution under irradiation (irradiation creep), physically based models of material mechanical properties post irradiation (hardening, local approach to fracture)

Responsable(s)

Emilie Ferrié, Guillaume Parry

Contenu(s)

  • C21 : Meso and Macroscopic effetcts of irradiation damage  (14h)
    • irradiation hardening (loops dislocation bubbles)
    • irradiation embrittlement, ductility reduction,  (Ductile Brittle Transition, Davidenkov diagrams - Considere diagrams)
    • irradiation creep and growth
    • swelling
    • general mechanisms of corrosion in nuclear environment, irradiation assisted  stress corrosion cracking  (2h)
  • C22 :  Fracture mechanics (14h)
    • Multi axial loading, triaxiality of stresses
    • Plain stress, plane strain
    • Non linear Fracture mechanics (basic linear elastic fracture mechanics will be given in module P1)
    • Introduction to Experimental fracture mechanics (tests - visual fractography) (1h)
    • Microstructural aspects of fracture (brittle, ductile, transgranular, intergranular, inclusions), SEM investigations  (2h)
    • Local approach to fracture (6h)
    • Modelling of ductile fracture (TD) (2h)

Bibliographie

Fundamentals of radiation sciences

Publications from Journal of Nuclear Materials