| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Wear Behavior of Incoloy™ 800HT and Inconel™ 617 for High-Temperature Gas-cooled Reactor (HTGR) Applications |
| Author(s) |
Valentin Pauly, Joseph Kern, Malcolm Clark, David S. Grierson, Kumar Sridharan |
| On-Site Speaker (Planned) |
Kumar Sridharan |
| Abstract Scope |
Incoloy™ 800HT and Inconel™ 617 are metallic materials that have been selected for structural applications in high-temperature gas-cooled reactors (HTGRs) based on their ASME code certification. Wear of rubbing components in HTGRs such as valves, valve seats, and valve shafts at high temperatures is of concern. Impurities (e.g., H2O and CH4) in the helium coolant induce corrosion reactions at high temperatures, and tribological performance will be strongly affected by the corrosion product layers that form on the components’ surfaces. Here we investigate the tribological behavior of Incoloy™ 800HT and Inconel™ 617 in the temperature range of 650°C to 900°C. We find that the presence of small concentrations of oxygen-bearing impurities are beneficial for wear resistance as they promote the formation of a compacted, hard, low-wear glaze-oxide layer. Surface modification treatments, such as aluminization, are also investigated to promote the formation of a glaze layer and improve tribological performance. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Mechanical Properties |