@article{oai:repo.qst.go.jp:00082843,
 author = {Katoh, Yutai and Vasudevamurthy, Gokul and Nozawa, Takashi and Dhan-Sham, Rana and Farnan, Ian and L. Snead, Lance and Takashi, Nozawa},
 journal = {Comprehensive Nuclear Materials (Second Edition)},
 month = {Aug},
 note = {Zirconium carbide (ZrC) is a potential coating, oxygen-gettering, or inert matrix material for advanced high temperature reactor fuels. ZrC has demonstrated attractive properties for these fuel applications including excellent resistance against fission product corrosion, fission product retention capabilities, and hydrogen corrosion resistance. However, fabrication of ZrC results in a range of stable sub-stoichiometric and carbon-rich compositions with or without substantial microstructural inhomogeneity, textural anisotropy, and a phase separation, leading to variations in physical, chemical, thermal, and mechanical properties. The effects of neutron irradiation at elevated temperatures, currently only poorly understood, are believed to be substantially influenced by those compositional and microstructural features further adding complexity to understanding the key ZrC properties. This article provides a survey of properties data for ZrC in support of the efforts toward fuel performance modeling and providing guidance for future research on ZrC for fuel applications.},
 pages = {419--456},
 title = {Properties of Zirconium Carbide for Nuclear Fuel Applications},
 volume = {7},
 year = {2020}
}