Zirconium carbide (ZrC) is being considered for utilization in high temperature gas cooled reactor fuels in deep burn TRISO fuel (Wongsawaeng, 2010). Zirconium carbide exhibits high melting point, exceptional hardness and good thermal and electrical conductivities. The use of ZrC in TRISO fuel requires a thorough understanding of its irradiation response, which is, however, still poorly understood. The majority of the research to date has focused on the radiation damage phenomena at higher temperatures (>450°C), where many fundamental aspects of defect production and kinetics cannot be easily distinguished.

 

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