About this Abstract |
Meeting |
2020 TMS Annual Meeting & Exhibition
|
Symposium
|
Additive Manufacturing for Energy Applications II
|
Presentation Title |
Irradiation Damage of 316L Stainless Steel Fabricated by Directed Energy Deposition |
Author(s) |
Ching-Heng Shiau, Cheng Sun, Michael McMurtrey, Randall Scott, Robert O’Brien |
On-Site Speaker (Planned) |
Ching-Heng Shiau |
Abstract Scope |
The flexibility enabled by additive manufacturing for fabrication have gained the growing interest of nuclear industry. The unique processing method, involving high temperature gradients and cooling rates, can introduce features such as sub-grained structures, pores and interfaces into the microstructure of materials. The distinctive microstructure in additive manufacturing alloy results in more varied behavior of mechanical properties than conventional wrought materials. The evolution of additive features under irradiation is still unknown and could play a crucial role in mitigating irradiation damage in materials. Additive manufacturing (AM) 316L stainless steel was fabricated via directed energy deposition. The microstructure evolution in AM 316L stainless steel under 2 MeV proton irradiation at 360℃ to 1 and 5 dpa are reported. The study on irradiation damage of AM 316L stainless steel provides new insights on the understanding and design of additive manufactured materials for nuclear core components. |
Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |