| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-based Composites for Nuclear Fission Applications
|
| Presentation Title |
Mechanical and Thermophysical Properties of ZrC, NbC, and TaC Binary Carbide Surrogate Fuels for Nuclear Thermal Propulsion Systems |
| Author(s) |
Alexander Nadermann, Jonas Kessing, Brandon Shaver, Justin Milner, Kelsa Palomares, Steven Zinkle |
| On-Site Speaker (Planned) |
Alexander Nadermann |
| Abstract Scope |
Nuclear Thermal Propulsion (NTP) fuel systems for in-space propulsion must survive extreme environments (>2700 K in the presence of flowing hydrogen). Solid solution carbide fuels are a promising option. Of the refractory metal carbides of interest, zirconium carbide (ZrC), niobium carbide (NbC) and tantalum carbide (TaC) were studied. ZrC, NbC, and TaC powders were consolidated in monocarbide (ZrC, NbC, TaC) and bi-carbide (ZrC-NbC, ZrC-TaC, NbC-TaC) forms using spark plasma sintering (SPS), with compositions ranging from 25 to 75 mol%; we will present results for the 50-50 mol% compositions of the bi-carbides. Final sintered densities >96% ideal density were achieved. The following thermophysical and mechanical properties were measured for each monocarbide and bi-carbide: specific heat capacity, thermal conductivity, coefficient of linear thermal expansion, Young’s modulus, shear modulus, Poisson’s ratio, hardness, flexural strength, and fracture toughness. These properties are essential to the understanding of the fundamental performance of the ternary carbide system. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Ceramics, High-Temperature Materials |