The SiC layer integrity in the TRISO-coated gas-reactor fuel particle is critical to the performance, allowed burn-up, and hence intrinsic efficiency of high temperature gas cooled reactors. While there has been significant developmental work on manufacturing the fuel particles, detailed understanding of the effects of the complex in-service stress state combined with realistic materials property data under irradiation on fuel particle survival is not adequately understood. This particularly frustrates the modeling efforts that seek to improve fuel performance through basic understanding. In this work a compilation of non-irradiated and irradiated properties of SiC are provided and reviewed and analyzed in terms of application to TRISO fuels. In addition to a compilation and review of literature data, new data generated to fill holes in the existing database is included, specifically in the high-temperature irradiation regime. Another critical piece of information, the strength of the SiC/Pyrolytic carbon interface, was measured and is included, along with a formalism for its analysis. Finally, recommended empirical treatments of the data are suggested.
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering