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