About this Abstract |
| Meeting |
MS&T26: Materials Science & Technology
|
| Symposium
|
Additively Manufactured Materials for Nuclear Energy
|
| Presentation Title |
Ion Irradiation Response of Additively Manufactured GRX-810 Medium-Entropy Oxide Dispersion Strengthened Alloy |
| Author(s) |
Hyosim Kim, Nicholas Evan Barta, Timothy M. Smith, Jonathan Gregory Gigax, Omar Roberto Mireles, Matthew Chancey, Miguel Pena, Yongqiang Wang |
| On-Site Speaker (Planned) |
Hyosim Kim |
| Abstract Scope |
Additively manufactured (AM) GRX-810 is an oxide dispersion strengthened (ODS) medium-entropy alloy (MEA) specifically designed for laser powder bed fusion, offering exceptional high-temperature strength, oxidation resistance, and creep performance up to 1200 °C. These properties make GRX-810 a promising candidate for advanced fission and fusion reactor applications. While ODS alloys are generally known for enhanced radiation tolerance, the irradiation response of GRX-810 remains unexplored. This study investigates the microstructural evolution of AM GRX-810 following nickel ion irradiation across varying temperatures and damage doses to simulate relevant reactor conditions. Post-irradiation characterization is compared with unirradiated controls to evaluate defect evolution, phase stability, and radiation-induced degradation mechanisms. This work represents the first systematic assessment of GRX-810 under reactor-relevant irradiation environments, providing critical insight into its viability as a next-generation radiation-resistant structural material. |