About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
| Presentation Title |
Deformation Characteristics of Additively Manufactured 316L Stainless Steels after Neutron Irradiation |
| Author(s) |
Thak Sang Byun, Maxim N. Gussev, Timothy G. Lach, Annabelle Le Coq, Kory Linton |
| On-Site Speaker (Planned) |
Thak Sang Byun |
| Abstract Scope |
Rapid solidification and cooling in the laser powder bed fusion process can produce a unique metastable microstructure in austenitic stainless steels (SSs), with ultrafine grains, high-density dislocations, and residual stresses. Such an additively manufactured (AM) microstructure with high defect sink density can offer desirable mechanical performance for nuclear application, including a superior combination of high strength, high ductility, and excellent radiation resistance. Neutron irradiation of miniature 316L SS tensile specimens was carried out in the high flux isotope reactor to 0.2, 2 and 8 dpa at 300 and 600 °C, and post-irradiation testing in selected conditions. This presentation is to discuss the deformation characteristics and mechanical properties of the AM SSs before and after neutron irradiation. We will elucidate unique post-irradiation plasticity behaviors observed in the austenitic structures, including the radiation-induced softening and ductilization in AM structures and serrated yielding (i.e., dynamic strain aging behavior) at high temperatures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Additive Manufacturing, Mechanical Properties |