Metallurgy and properties of Zr alloys for nuclear applications
• 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.
Students carrying out specialised studies on materials science and nuclear engineering.
- 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 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.
- Technical visits.
- Reactor feedback and future trends in design and requirements.
Maximum number of trainees: 25.
5 days (30 hours)
- 2-6 December 2019
M. Bertrand REYNIER
Phone number: +33 1 69 08 48 75
Mme Irfana GUELAH
Phone number: +33 1 69 08 58 50
No training session is currently scheduled for 2020. Contact us.