| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Irradiation Testing: Facilities, Capabilities, and Experimental Designs
|
| Presentation Title |
Irradiation Testing of 316H Stainless Steel at Oak Ridge National Laboratory |
| Author(s) |
Annabelle G. Le Coq, Caleb Massey, Patrick Champlin, Richard Howard, Kory Linton |
| On-Site Speaker (Planned) |
Annabelle G. Le Coq |
| Abstract Scope |
Neutron irradiations performed at Oak Ridge National Laboratory (ORNL) under the Advanced Materials and Manufacturing Technologies program aim to generate irradiated material properties information in support of establishing a technical basis for regulatory acceptance of advanced materials. Leveraging the ORNL’s High Flux Isotope Reactor, high-throughput and accelerated testing is performed to demonstrate a rapid qualification framework. 316H stainless steel (SS) was fabricated at ORNL using advanced manufacturing for initial screening of the material’s mechanical properties and microstructure response post-irradiation. This paper highlights the irradiation vehicles selected for HFIR irradiation of 316H SS such as the standardized tensile and the newly developed fracture toughness capsule design, and describes the irradiation test matrix. This initial screening of 316H SS specimens using ORNL’s irradiation and post-irradiation capabilities will precede evolved screening and qualification relevant testing of this advanced material. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, |