About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
High Temperature X-ray and Neutron Studies of Uranium Carbide Systems |
| Author(s) |
Xiaofeng Guo, William Vance, Matthew Heaney, Emma C. Kindall, Shinhyo Bang, Natalie S. Yaw, John S. McCloy, Adrien J. Terricabras, Scarlett Widgeon Paisner, Arjen van Veelen, Joshua T. White |
| On-Site Speaker (Planned) |
Xiaofeng Guo |
| Abstract Scope |
UC has several key characteristics with the industry standard, making it a strong candidate for use in emerging Generation IV advanced reactors, both as pristine fuels and as kernels in accident tolerant TRISO fuels. A fundamental understanding of the material chemistry and thermodynamic properties of U-C system is critical for predicting behavior under reactor, off-normal, or storage conditions. Here we employ in situ high temperature neutron and X-ray diffraction to investigate the thermal behavior and thermophysical parameters of uranium monocarbide (UC), and two other uncommon but important phases uranium dicarbide (UC2) and uranium sesquicarbide (U2C3) across the temperature range from ambient to 950℃. We reported temperature dependent thermal expansion coefficients (CTE) and atomic displacement coefficients of both U and C, for all three phases. In high temperature XRD experiments, we confirmed CTE of UC, and also reveal the possibility of formation of UC2 during low-oxygen partial pressure conditions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Ceramics, Nuclear Materials |