| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Additive Manufacturing Materials in Energy Environments II
|
| Presentation Title |
Post Irradiation Examination of Neutron-Irradiated AM 316L Stainless Steel |
| Author(s) |
Timothy G. Lach, Stephen Taller, Caleb Massey |
| On-Site Speaker (Planned) |
Timothy G. Lach |
| Abstract Scope |
Additive Manufacturing (AM) has greatly improved the ability to efficiently manufacture complex parts for a wide range of applications including nuclear reactors. Neutron irradiation and post irradiation examination campaigns are necessary to understand how radiation effects depend on initial microstructure based on AM vs conventional processing and how that affects microstructural evolution and mechanical behavior. This work sought to study the evolution of cavities, dislocation structure, and elemental segregation and precipitation in LPBF 316L stainless steel under neutron irradiation and the correlation with the property changes. As-printed material before and after annealing were irradiated at ORNL’s High Flux Isotope Reactor to doses of 0.2, 2, and 10 dpa at target temperatures of 300°C and 600°C. Analytical electron microscopy and atom probe tomography examined the microstructural evolution as a function of irradiation temperature, dose, and initial microstructure. This work will provide insights into the use of AM steels in radiation environments. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Additive Manufacturing, Nuclear Materials, Characterization |