|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Thermomechanical characterization of advanced reactor alloys and composites exposed to high-temperature gas environments
||William Searight, Leigh Winfrey
|On-Site Speaker (Planned)
Advanced reactors have much more demanding operating environments than current commercial power reactors in terms of high temperature/heat flux, radiation flux and corrosion. To enable commercial development of these reactors, structural materials must be developed to survive these environments for extended operation without maintenance. In this work, samples of Silicon Carbide fiber-reinforced matrix composite (SiC/SiC), TiZrMo alloy and Highly Oriented Pyrolytic Graphite (HOPG) have been selected for their potential of long-term endurance in high-temperature and corrosive environments. These samples will be held in a backfilled tube furnace at 1400 °C for 100-200 hours (dependent on gas resources) to identify thermomechanical property degradation in gas mixtures of argon, hydrogen, and helium. Surface composition and microstructure will be analyzed using Scanning Electron Microscopy (SEM) techniques, and thermomechanical properties using Thermogravimetric Analysis (TGA) and microindentation. Time of Flight Secondary Ion Mass Spectroscopy (TOF SIMS) will be used to map hydrogen content post-exposure.
||Characterization, High-Temperature Materials, Mechanical Properties