| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Thermomechanical Characterization of Advanced Reactor Alloys and Composites Exposed to High-temperature Gas Environments |
| Author(s) |
William Searight, Leigh Winfrey |
| On-Site Speaker (Planned) |
William Searight |
| Abstract Scope |
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 TZM 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 were held in a backfilled tube furnace at 1240 °C for 40 hours to identify thermomechanical property degradation in gas mixtures of argon, hydrogen, and helium. Surface composition and microstructure were analyzed using Scanning Electron Microscopy (SEM) techniques, XRD and optical profilometry and thermomechanical properties using Thermogravimetric Analysis (TGA) and microindentation. Time of Flight Secondary Ion Mass Spectroscopy (TOF SIMS) was used to map hydrogen content of TZM post-exposure. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, High-Temperature Materials, Mechanical Properties |