|About this Abstract
||2020 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
||Three-dimensional Analysis of the IPyC/SiC Interface in Irradiated TRISO Fuel Particles
||Tyler J. Gerczak, Rachel Seibert
|On-Site Speaker (Planned)
||Tyler J. Gerczak
The silicon carbide (SiC) layer of tristructural-isotropic (TRISO) coated particle is the primary barrier to release of fission products not retained in the fuel kernel. However, diffusion into and reaction with the SiC layer has been observed for select fission products (e.g. palladium and silver). The nature of the inner pyrolytic carbon (IPyC)/SiC interface likely governs the interaction of these fission products with the SiC layer. Three-dimensional reconstruction image analysis of the IPyC/SiC layer from as-fabricated TRISO particles are compared with the IPyC/SiC interface from irradiated particles from the AGR-2 irradiation experiment with varying silver retention behaviors. The analysis provides a quantitative description of the IPyC/SiC interface – IPyC/SiC interface stitching and open porosity – as well as insights into their influence on fission product interactions with the SiC layer.