|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Evolution of Ion Irradiated Nitride Ceramics Properties for Coated Particle Fuel Systems
||Adrien J. Terricabras, Alicia M. Raftery, Andrew T. Nelson, Steven J. Zinkle
|On-Site Speaker (Planned)
||Adrien J. Terricabras
Novel coated particle fuel systems are of particular interest within the research community lately with possible applications ranging from space reactors to Small Modular Reactors and more. Using a uranium oxycarbide or uranium nitride core with alternative coatings such as ZrC or ZrN, they are designed to alleviate current TRISO shortcomings such as loss of integrity of the SiC layer and fission product attacks. Ion irradiation was performed on polycrystalline Si3N4 and ZrN using 15 MeV Ni5+ ions. Midrange doses varied from 1 to 50 dpa and temperatures from 300 to 700 °C. Thermal conductivity of the ion irradiated region was measured using thermal wave methods. Volumetric lattice swelling of the ceramics was determined by grazing incidence X-ray diffraction. Defect evolution was tracked using Transmission Electron Microscopy, while nanoindentation was performed to quantify the ceramics’ mechanical properties evolution. The nitrides behavior will be compared with SiC and other ceramics.