About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Accelerated Deployment of Advanced Reactors – A Predictive Pathway for Rapid Qualification of Core Structural Materials |
| Author(s) |
Gary S. Was, Kevin Field, Valentin Pauly, Brian Wirth, Steven Zinkle, Arthur Motta, Xing Wang, Stephen Taller |
| On-Site Speaker (Planned) |
Gary S. Was |
| Abstract Scope |
Key to the accelerated deployment of advanced reactors is rapid qualification of core materials. The lack of test reactor availability, the extensive irradiation time required, and the resulting high cost make traditional routes to obtain the data needed to qualify core materials impractical in the near term. Ion irradiation coupled with advanced, rapid characterization constitute a solution to this dilemma. Using one ferritic-martensitic alloy and one austenitic alloy, we show that the key microstructure and mechanical properties created in reactor can be replicated with ion irradiation. Computational materials modeling is used to inform the ion irradiation parameters and to provide predictive capability of material properties. Results from this methodology are benchmarked against reactor data on the same alloy, and codified in ASTM standards, thus providing licensees with a justification of the efficacy of their core material performance when establishing their safety case for the regulator. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Modeling and Simulation |