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.
- 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