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Metallurgy and properties of zr alloys for nuclear applications

The objective of the module is to acquire a general view of Zr alloys from the processing to in service properties including safety concerns.

Upon completion, participants will be able to:

  • 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 scenario;
  • Give a reactor feedback and next future trends. 

Content:

  • 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, texture development, mechanical properties
  • Irradiation effects. Effects on microstructure. Creep and growth.
  • Mechanical behavior after irradiation
  • Corrosion in water (without and under irradiation)
  • High temperature oxidation and LOCA behavior
  • Impact of H Pick-up: embrittlement, RIA, post irradiation creep
  • Technical visits
  • Reactor feedback and future trends in design and requirements
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