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Irradiation Assisted Stress Corrosion Cracking (IASCC) is a materialdegradation phenomenon affecting austenitic stainless steels used in nuclearPressurized Water Reactors (PWR), leading to the initiation and propagation ofintergranular cracks. Such phenomenon belongs to the broader class ofInterGranular Stress Corrosion Cracking (IGSCC). A micromechanical analysis ofIGSCC of an irradiated austenitic stainless steel is performed in this study toassess local cracking conditions. A 304L proton irradiated sample tested in PWRenvironment and showing intergranular cracking is investigated. Serialsectioning, Electron BackScatter Diffraction (EBSD) and a two-step misalignmentprocedure are performed to reconstruct the 3D microstructure over an extendedvolume, to assess statistically cracking criteria. A methodology is alsodeveloped to compute Grain Boundary (GB) normal orientations based on the EBSDmeasurements. The statistical analysis shows that cracking occurspreferentially for GB normals aligned with the mechanical loading axis, butalso for low values of the Luster-Morris slip transmission parameter.Micromechanical simulations based on the reconstructed 3D microstructure,FFT-based solver and crystal plasticity constitutive equations modified toaccount for slip transmission at grain boundaries are finally performed. Thesesimulations rationalize the correlation obtained experimentally into a singlestress-based criterion. The actual strengths and weaknesses of suchmicromechanical approach are discussed.

A micromechanical analysis of intergranular stress corrosion cracking of an irradiated austenitic stainless steel