Abstract
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 what effects the complex in-service stress state combined with realistic materials property data under irradiation has on fuel particle survival is not adequately understood. This fact particularly frustrates the modeling efforts that seek to improve fuel performance through basic understanding. In this work the properties of SiC in the non-irradiated and irradiated condition are reviewed and analyzed in terms of applicability to TRISO fuel modeling. In addition to a review of literature data, new data has been generated to fill-in holes in the existing database, specifically in the high-temperature irradiation regime. Another critical piece of information, the strength of the SiC/Pyrolytic carbon interface, is measured and a formalism for its analysis presented. Finally, recommended empirical treatments of the data are suggested.
