| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Mechanical Behavior and Radiation Effect in Additively Manufactured 316L Stainless Steel |
| Author(s) |
Meimei Li, Xuan Zhang, Wei-Ying Chen |
| On-Site Speaker (Planned) |
Meimei Li |
| Abstract Scope |
Additive manufacturing (AM) as a disruptive manufacturing technology enables smart designs of nuclear reactor components with complex geometries and provide unprecedent design freedom. It also opens up new opportunities for designing advanced materials with controlled microstructure and properties. This paper summaries the recent effort on investigating the high-temperature mechanical behavior and radiation response of AM 316L SS for its core structural applications in the Transformational Challenge Reactor, a gas-cooled microreactor being developed to demonstrate revolutionary technologies including additive manufacturing. Creep and fatigue behavior of AM 316L stainless steel and the effect of post-build heat treatment was evaluated. Deformation mechanisms in AM 316L stainless steel was studied by synchrotron high-energy X-ray techniques. The evolution of irradiation-induced defects in AM 316L SS was investigated by in situ ion irradiation with transmission electron microscopy. |
| Proceedings Inclusion? |
Planned: |