| About this Abstract |
| Meeting |
Materials Science & Technology 2019
|
| Symposium
|
Materials for Nuclear Applications
|
| Presentation Title |
P3-62: Characterization and Oxidation of Graphite and Silicon Carbide in TRISO Nuclear Fuel |
| Author(s) |
Adam T. Bratten, Jiaqi Duan, Hans Pommerenke, Haiming Wen |
| On-Site Speaker (Planned) |
Adam T. Bratten |
| Abstract Scope |
In order to advance the development of high-temperature gas reactors (HTGRs), it is important to assess the integrity of the tristructural-isotropic (TRISO) coated fuel particles and the graphitic matrix (which binds these fuel particles together) during accident scenarios. This includes investigation of oxidation of graphite and silicon carbide during air and moisture ingress into the helium loop. TRISO particles and matrix-grade graphite were characterized before and after oxidation in oxygen and steam environments. Characterization included optical microscopy, scanning electron microscopy, X-ray diffraction, and X-ray computed tomography. Combined thermogravimetric analysis and differential scanning calorimetry was performed to determine the oxidation rates and compare two grades of matrix graphite (A3-3 and A3-27). Pre-oxidation results on graphite and TRISO particles are discussed as well as oxidation results obtained from TGA/DSC and high-temperature furnace experiments. |