| About this Abstract |
| Meeting |
2016 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Fuels for the Current and Advanced Nuclear Reactors V
|
| Presentation Title |
Grain Orientation Factor and Stress Corrosion Crack Initiation in Neutron-irradiated Austenitic Stainless Steels |
| Author(s) |
Maxim N. Gussev, Kevin G. Field, Jeremy T. Busby, Kale J. Stephenson , Gary S. Was |
| On-Site Speaker (Planned) |
Maxim N. Gussev |
| Abstract Scope |
Susceptibility to irradiation-assisted stress corrosion cracking (IASCC) is widely recognized as one of the most severe degradation issues for austenitic stainless steels. In the present work, detailed analysis of stress corrosion crack initiation was conducted using irradiated tensile specimens subjected to constant extension tensile tests in a simulated primary water (PW) environment. Strain localization, crack initiation, and crack propagation path were investigated using SEM-EBSD and (S)TEM. It was found that crack initiation required some local plastic strain, roughly 0.5-0.7% for 10.2-dpa irradiated commercial 304 steel. Cracks were initiated readily, but their propagation was suppressed in the PW-environment. Some specific phenomena accompanying straining and corrosion in high-temperature water (slip line oxidation, retained ferrite behavior) are discussed. The role of grain orientation was analyzed in detail; it was observed that cracks often initiated at GBs adjacent to at least one grain with [111]-orientation relative to the tensile axis. |
| Proceedings Inclusion? |
Planned: A print-only volume |