About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications II
|
| Presentation Title |
Thermal Properties of Dispersoid-strengthened Tungsten Alloys for Fusion Applications |
| Author(s) |
Chase C. Hargrove, Trevor Marchhart, Nathan Reid, Xing Wang, Jean Paul Allain |
| On-Site Speaker (Planned) |
Chase C. Hargrove |
| Abstract Scope |
Tungsten (W) is a candidate as a plasma facing component in the divertor region of fusion tokamaks due to its high yield strength and melting point (3422°C), and low coefficient of linear thermal expansion at elevated temperatures relative to other refractory metals. As a PFC, W will be exposed to short (ms) pulsed heat loads on the order of GW/m2. The effects of carbide additions on the thermal properties of W warrant further study as these are essential to the thermal shock and fatigue response. W-TaC samples fabricated via spark-plasma sintering (SPS) have been shown to possess a lower thermal conductivity than pure W; this behavior is intrinsically dependent on the microstructure. In this work, samples of W-TaC, W-TiC, and W-ZrC are fabricated via SPS. Thermal conductivity is calculated from the measured electrical resistivity.
Work supported by DOE Contract DE-SC0021119 |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Characterization, Other |