About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
In-situ irradiation of zirconium carbide and zirconium nitride above 800°C |
| Author(s) |
Rashed Almasri, Jian Gan, Yuhan Li, Wei-Ying Chen, Lingfeng He |
| On-Site Speaker (Planned) |
Rashed Almasri |
| Abstract Scope |
Zirconium carbide (ZrC) and zirconium nitride (ZrN) show potential for future applications in nuclear reactors, like coatings in the TRISO fuels and surrogate materials for uranium carbide (UC) and uranium nitride (UN), respectively. ZrC and ZrN were irradiated using the Intermediate Voltage Electron Microscope (IVEM) with Kr ions at high temperatures ranging from 800 to 1100°C. In-situ transmission electron microscopy (TEM) was used to show the dislocation loop evolution as a function of irradiation temperature and dose. Xe ion irradiation was also done at 800°C with higher doses to observe the growth of Xe gas bubbles as a function of irradiation dose. Swelling was calculated by analyzing the bubble size and density in the TEM images taken during and after irradiation. ZrC and ZrN were directly compared to UC and UN, respectively to evaluate their potential as surrogates. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Nuclear Materials, High-Temperature Materials |