Materials for Nuclear Reactors, Fuels and Structures course

Learning outcomes: identify the major materials used in nuclear reactors: Steels, Zr alloys and carbides, analysis the mechanisms of the irradiation effects on the materials, describe the evolution of the microstructure and the impact induced by irradiation on the properties of the major materials.

• Mechanisms of irradiation damage: neutrons, photons, electrons
• Behavior 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