The course addresses the following items:
– 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
– Enhanced-Accident-Tolerant-Fuels » (E-ATF) coated Zr claddings
The training allows participants to acquire a general view of Zr alloys from the processing to in service properties including safety concerns. At the end of the course, they 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 scenarii,
– Give a reactor feedback and next future trends.
You are qualified engineers, scientists and technicians in charge of fabrication, characterization, application and safety evaluations of Zr based components for nuclear purposes, or students carrying out specialised studies on material science and nuclear engineering.
Participation fees are from 2170€ per person.
For registration, please contact the course owner/assistant or follow the registration link that will drive you to the course page with contact details.
2026 implementation date is under review. For privatized sessions, please contact us.