| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Mitigation of Irradiation-Assisted Stress Corrosion Cracking by Laser Annealing |
| Author(s) |
Maayan Matmor, Jonathan Tatman, Mitch Hargadine, Peter Chou, Peter Hosemann |
| On-Site Speaker (Planned) |
Maayan Matmor |
| Abstract Scope |
Currently, mitigation against irradiation-assisted stress corrosion cracking (IASCC) in stainless steel surfaces is primarily achieved through the use of hydrogenated water chemistry in Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs), known as Hydrogen Water Chemistry and its variants. Despite these measures, instances of IASCC continue to occur and are expected to increase with long-term reactor operation.
This study proposes an economically viable mitigation method utilizing laser-induced lattice strain annealing. Cold-worked 316L stainless steel with 10%-30% axial deformation was employed as a surrogate for irradiated samples. Various laser setups were tested to eliminate near-surface defects that could potentially propagate into IASCC during future service. The effects of cold work and laser treatment on the microstructure, lattice strain, and mechanical properties were assessed using nanoindentation and Electron Backscatter Diffraction (EBSD). The results demonstrate that laser annealing effectively reduced lattice strain and improved the material's resistance to IASCC. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Other |