A micromechanical analysis of intergranular stress corrosion cracking of an irradiated austenitic stainless steel
D. Liang, J. Hure, A. Courcelle, S. El Shawish, B. Tanguy

TL;DR
This study combines experimental microstructure analysis and micromechanical simulations to understand intergranular stress corrosion cracking in irradiated stainless steel used in nuclear reactors.
Contribution
It introduces a novel methodology integrating 3D microstructure reconstruction, EBSD analysis, and crystal plasticity simulations to predict cracking conditions in irradiated stainless steel.
Findings
Cracking occurs mainly along grain boundaries aligned with the load axis.
Low Luster-Morris slip transmission parameter values are associated with cracking.
The stress-based criterion successfully explains the experimental observations.
Abstract
Irradiation Assisted Stress Corrosion Cracking (IASCC) is a material degradation phenomenon affecting austenitic stainless steels used in nuclear Pressurized Water Reactors (PWR), leading to the initiation and propagation of intergranular cracks. Such phenomenon belongs to the broader class of InterGranular Stress Corrosion Cracking (IGSCC). A micromechanical analysis of IGSCC of an irradiated austenitic stainless steel is performed in this study to assess local cracking conditions. A 304L proton irradiated sample tested in PWR environment and showing intergranular cracking is investigated. Serial sectioning, Electron BackScatter Diffraction (EBSD) and a two-step misalignment procedure are performed to reconstruct the 3D microstructure over an extended volume, to assess statistically cracking criteria. A methodology is also developed to compute Grain Boundary (GB) normal orientations…
Peer Reviews
No public reviews on file for this paper yet. If you reviewed it on a platform where reviews are public (OpenReview, ICLR, NeurIPS, ICML), you can paste yours below so the community can read it here.
Videos
No videos yet. Explain this paper in a talk, walkthrough, or lecture? Add one.
