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DOE OSTI · 3385005

Stoichiometric effects on grain growth in zirconium carbide coatings for high-temperature nuclear fuel

Abstract

Interest in coated particle fuel for space nuclear propulsion (SNP) has expanded in recent years due to successful demonstrations of the resiliency of the coatings to extreme environments. For SNP applications, the coating layer for the particle design needs to be able to withstand exposure to high temperature hydrogen during operating conditions. ZrC has been proposed as a protective layer, however, it is important to understand the high temperature behavior to ensure adequate protection to this fuel. In this study, surrogate ZrC coated particles were heat treated at 1900 °C up to 300 min, to examine how the microstructure evolves when exposed to high temperature. Scanning electron microscopy and electron backscatter diffraction (EBSD) were conducted to determine grain size and grain boundary character and orientation to determine the degree of change in the ZrC layer post heat treatment. Raman spectroscopy provided insight to understand how the as-fabricated stoichiometry of each sample contributed to the differences in grain growth behavior. Despite the as-fabricated samples showing a similar initial grain size and grain boundary character, the samples with a higher amount of excess carbon exhibited smaller grain areas and slower growth rates when exposed to 1900 °C. In conclusion, this investigation details the as-fabricated microstructure of the ZrC layer, specifically grain size, evolved under high temperature as this can impact the performance of the fuel under operating conditions.

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BibTeXRIS

Montoya, Katherine I. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000326955086), Conry, Bryan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000236089604), Jones, J. Wesley [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:000900044014599X), Heldt, Ryan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0009000078176290), Gerczak, Tyler J. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000199673579), Honorato, Eddie Lopez [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:000000017948798X). 2026-10-01. Stoichiometric effects on grain growth in zirconium carbide coatings for high-temperature nuclear fuel. https://doi.org/10.1016/j.jnucmat.2026.156852

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