About this Abstract |
| Meeting |
2027 TMS Annual Meeting & Exhibition
|
| Symposium
|
Enabling Nuclear Materials Innovation via the Nuclear Science User Facility Capabilities
|
| Presentation Title |
Microstructural Evolution of Beryllium Carbide Under In Situ Dual-Ion Irradiation |
| Author(s) |
Diego Alejandro Muzquiz, Kevin Field , Stephen Raiman |
| On-Site Speaker (Planned) |
Diego Alejandro Muzquiz |
| Abstract Scope |
The development of advanced nuclear reactors has renewed interest in radiation-tolerant moderators capable of withstanding high-dose environments. Many proposed reactor concepts rely on solid-state moderators; however, the extreme conditions within the reactor core raise concerns regarding the long-term reliability of traditional moderator materials. In this work, beryllium carbide (Be₂C) is investigated as a potential next-generation moderator due to its favorable theoretical performance under harsh reactor conditions. To evaluate its radiation response, a series of in-situ dual-ion beam irradiations were conducted at 600 °C. Xenon ions were used to produce damage up to 30 dpa while simultaneously implanting either hydrogen (1200 appm) or helium (500 appm). Post-irradiation characterization was performed using electron energy-loss spectroscopy (EELS), and high-resolution transmission electron microscopy (HRTEM) to investigate microstructural evolution and fission gas effects. Initial observations reveal nanoscale recrystallization and limited nucleation of dislocation loops, suggesting a relatively high resistance to radiation under the investigated conditions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Ceramics, Nuclear Materials |