| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Irradiation Damage in High-entropy Carbide Ceramics |
| Author(s) |
Fei Wang, Xueliang Yan, Tianyao Wang, Yaqiao Wu, Lin Shao, Michael Nastasi, Yongfeng Lu, Bai Cui |
| On-Site Speaker (Planned) |
Bai Cui |
| Abstract Scope |
Novel high-entropy carbide ceramics (HECC) have been developed as a promising structural material for advanced reactor designs. (Zr0.25Ta0.25Nb0.25Ti0.25)C HECC with a single-phase rock-salt structure was synthesized by spark plasma sintering, which was irradiated by 3 MeV Zr ions to 20 dpa at 25, 300, and 500 ºC. X-ray diffraction analysis showed that (Zr0.25Ta0.25Nb0.25Ti0.25)C maintained a high phase stability without phase transformation after irradiation. About 0.2% lattice parameter expansion was revealed. The irradiation-induced microstructures were comprised of defect clusters with diameters of several nanometers, without void formation or radiation-induced segregation. The defect clusters were characterized by transmission electron microscopy as two types of dislocation loops, including perfect loops and faulted Frank loops. The growth of dislocation loops may be suppressed by the strong local lattice distortion. Nanoindentation tests showed irradiation-induced hardness increase, which was possibly caused by dislocation loops and lattice strain. |
| Proceedings Inclusion? |
Planned: |