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

Autor: A. Courcelle, D. Liang, J. Hure, Benoit Tanguy, S. El Shawish
Přispěvatelé: Service d'Etudes des Matériaux Irradiés (SEMI), Département des Matériaux pour le Nucléaire (DMN), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Laboratoire de Comportement Mécanique des Matériaux Irradiés (LCMI), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Département des Matériaux pour le Nucléaire (DMN), Laboratoire de Microscopie et d'Etudes de l'Endommagement (LM2E), Jozef Stefan Institute [Ljubljana] (IJS), The authors gratefully acknowledge financial support provided by Slovenian Research Agency (grant P2-0026) and French Atomic Energy Commission., CEA- Saclay (CEA), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
Jazyk: angličtina
Rok vydání: 2021
Předmět:
Zdroj: Acta Materialia
Acta Materialia, 2021, pp.116482. ⟨10.1016/j.actamat.2020.116482⟩
Acta Materialia, Elsevier, 2021, 204, pp.116482-. ⟨10.1016/j.actamat.2020.116482⟩
Acta Materialia, 2021, 204, pp.116482. ⟨10.1016/j.actamat.2020.116482⟩
ISSN: 1359-6454
DOI: 10.1016/j.actamat.2020.116482⟩
Popis: International audience; 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 alsodeveloped to compute Grain Boundary (GB) normal orientations based on the EBSD measurements. The statistical analysis shows that cracking occurs preferentially for GB normals aligned with the mechanical loading axis, but also 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 to account for slip transmission at grain boundaries are finally performed. These simulations rationalize the correlation obtained experimentally into a single stress-based criterion. The actual strengths and weaknesses of such micromechanical approach are discussed.
Databáze: OpenAIRE