Zirconium carbide (ZrC) is a candidate material for use in one of the layers of TRISO coated fuel particles to be used in the Generation IV high-temperature, gas-cooled reactor, and thus it is necessary to study the effects of radiation damage. The microstructural evolution of ZrC x under irradiation was studied in situ using the Intermediate Voltage Electron Microscope (IVEM) at Argonne National Laboratory. Samples of nominal stoichiometries ZrC 0.8 and ZrC 0.9 were irradiated in situ using 1 MeV Kr 2+ ions at various irradiation temperatures (T = 20 K-1073 K). In situ experiments made it possible to continuously
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