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Metallurgy and properties of Zr alloys for nuclear applications

Cycle du combustible

Matériaux

Matériaux pour le nucléaire

Métallurgie

4.7
Note moyenne de satisfaction des participants
© Bertrand REYNIER INSTN/UES

En bref

The aim of this training is to present the main Zirconium-based alloys in pressurised water reactors, to understand their properties and in-service behaviour under thermo-mechanical and chemical stresses and under strong irradiation.

A qui s’adresse cette formation ?

Qualified engineers, scientists and technicians in charge of fabrication, characterization, application and safety evaluations of Zr based components for nuclear purposes; Students carrying out specialised studies on materials science and nuclear engineering

Compétences visées

Acquire a general view of Zr alloys from the processing to in service properties including safety concerns:

  • Highlight the main processing parameters affecting the as-received material properties;
  • Explain the relationship between the microstructure evolution and the physico-chemical and mechanical properties: under irradiation, during corrosion, oxidation and hydriding in light water reactors environment, under accidental scenarii
  • Give a reactor feedback and next future trends.
  • Lectures are given by academic and professional experts  of recognized standing in Material Sciences.
  • Practical work on actual fuel cladding specimen after thermal treatments and with or without chrome plating (SEM observations)
  • History and overview of Zr alloys for nuclear applications
  • Processing and forming of industrial components
  • Phase diagrams (includes Zr-H and Zr-O) and control of microstructures (in Zry and Zr-Nb)
  • Anisotropy, deformation mechanisms, cristallographic texture development, mechanical properties
  • Irradiation effects : Effects on microstructure; Creep and growth
  • Mechanical behaviour after irradiation
  • Corrosion in water (without and under irradiation)
  • High temperature oxidation and LOCA behaviour
  • Impact of H Pick-up: embrittlement, RIA, post irradiation creep
  • Reactor feedback and future trends in design and requirements for fuel cladding

 Basic skills in material science are required

Méthodes et outils pédagogiques

Contact(s)

INSTN Saclay

Contact administratif :

Irfana GUELAH
instn-ues-sac-af@cea.fr

Contact pédagogique :

Bertrand REYNIER
bertrand.reynier@cea.fr
+33 1 69 08 48 75

Sessions de formation

Groupe limité à 9 Personnes

Si vous êtes en situation de handicap, veuillez contacter le référent handicap, afin de vérifier les possibilités de mise en oeuvre de l'action de formation, à l'adresse suivante : instn-handicap@cea.fr

Du 13 mai 2024
Au 17 mai 2024 INSTN Saclay 2 560,00€ HT S'INSCRIRE

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