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Materials for nuclear reactors, fuels and structures - International school in nuclear engineering



Nuclear reactor

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In summary

Mechanisms of irradiation damage: neutrons, photons, electrons behaviour of materials under irradiation: ferritic steels for reactor pressure vessel, austenitic stainless steels for internals or fuel cladding (FBR), Zr alloys for fuel
cladding and fuel assemblies (LWR)
Zr alloys in accidental conditions and Enhanced Accident Tolerant Fuel claddings
Fuel materials (UO2, PuO2): irradiation-induced effects, Materials for high temperature conditions: SiC, ZrC, low swelling alloys
Materials for fusion: low activation materials, resistance to high-energy neutrons, breading blankets

Who should take this course ?

The doctoral course is designed for young researchers, PhD students, post-doctorates and engineers from nuclear industry companies, research centres, Universities, Technical Safety Organizations (TSO), regulatory bodies.

Learning outcomes

• Describe the mechanisms of irradiation damage.
• Identify the available techniques to investigate the evolution of materials under irradiation.
• Compare the properties of steels used for reactor core structures;
• Explain the evolution of fuel and cladding during operation.

- Mechanisms of irradiation damage.
- Introduction to fuel materials.
- Behaviour of in core metallic materials:
• Steels for LWR, FBR and fusion,
• Zr alloys for Fuel Assembly in LWR.
- Carbides, SiC and ZrC high temperature materials for GenIV reactors.

Minimum background: Master of Science in Nuclear Engineering or Materials Science.

Teaching method and tools


Program manager :

+33 1 69 08 93 29

training sessions

No training session is scheduled for the moment, if this training interests you, please contact us.

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