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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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Comparison of Nuclear Thermal Propulsion Reactor Cores Using Different Fuel Forms, Neutron Spectra, and Uranium Enrichments

A comparison of 300 MWt HEU and HALEU NTP cores using different fuel forms is presented to demonstrate trends and potentially inform fuel development. Compared to HEU, HALEU cores require additional in-core moderation. Beryllium was chosen as the reference in-core moderator material; metal hydrides may also be considered. Typical NTP fuel forms such as carbide and carbonitride solid solutions, carbide-graphite composites, CERMETs and CERCERs were considered together with less typical fuel forms such as UC and U metal. Be-moderated HALEU cores are heavier than HEU cores (1.9-2.7 and 0.9-2.0 metric tons, respectively). Furthermore, HALEU loading is very sensitive to the amount of in-core moderation which translates into tight fabrication tolerances. HALEU cores requires more reactivity control mechanisms than HEU cores to compensate for temperature feed-back. Using enrichments only slightly above HALEU (e.g., 25%) may provide a compromise between the administrative preference for using HALEU and the engineering preference for simplifying the reactor systems by, for example, not using in-core moderators.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Thermochemistry of Aerospace Materials

The reliability and development of aerospace materials in extreme environments relies on a comprehensive understanding of their thermochemical properties. Such properties are commonly used for equilibrium phase stability calculations of interactions with corrosive environments at very high temperatures. These calculations can lead to in-depth understanding of degradation mechanisms in both coatings and components for applications such as nuclear thermal propulsion and gas turbine engines, both of which are part of NASA’s current R&D focus for improving propulsion systems for aerospace missions. The first part of this talk summarizes and discuss our current thermochemical calculations of the behavior of ceramic-ceramic (cercer) UN-based fuels and their coating systems during nuclear thermal rocket operation. The second part of the talk summarizes and discuss the energetics of reactions of ceramic coating materials and their binary oxide components with silicate melts measured by high temperature reaction calorimetry.

Nuclear Thermal propulsion↗