| Abstract Scope |
Recent interest in direct nuclear thermal propulsion (NTP) has correlated with developments and investment in ZrC-based materials, since alloying Zr with 10-30 at% uranium ((U,Zr,X)C) provides one of the most promising solid fuel candidates. Conceptual fabrication, process science, and expected properties of ZrC and (U,Zr)C-based materials are discussed. Four key development areas stand out; first, outstanding questions in key thermal and physical properties. In addition, solid-solution carbides are candidates in hypersonics and fusion materials. Process science, particularly pressureless sintering, have been identified as areas for improvement. Finally, swelling is the only burnup property of (U,Zr)C that has been reported, and illustrates challenges for longer term missions. Collectively, these represent key hurdles for the nuclear community to address in order to support the institutions leading the space nuclear effort. |