| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Mechanical Properties of Additively Manufactured 316L Stainless Steel before and after Neutron Irradiation |
| Author(s) |
Thak Sang Byun, Timothy Lach, Maxim Gussev, Kurt Terrani |
| On-Site Speaker (Planned) |
Thak Sang Byun |
| Abstract Scope |
The Transformational Challenge Reactor (TCR) program plans to build most core components through additive manufacturing (AM) processes, including the laser powder bed fusion (LPBF) for the metallic (316L) components. Mechanical testing and microstructural characterization before and after irradiation have been performed to build a database and assess the performance of AM components in reactor conditions. This presentation is to discuss the outcome of those activities focusing on the mechanical performance of AM 316L stainless steel. Baseline and post-irradiation tensile testing over a wide temperature range of room temperature–600°C were performed for the AM 316L alloy in as-built, stress-relieved, and solution-annealed conditions. The AM 316L stainless steel, regardless of its post-build processing, showed higher strength and comparable ductility compared to those of wrought 316L stainless steel. Mechanical property data indicate that the AM 316L stainless steel demonstrates a high resistance to the neutron irradiation at 300°C and 600°C. |
| Proceedings Inclusion? |
Planned: |