About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Composite Materials for Nuclear Applications II
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Presentation Title |
Thermal Properties of Dispersoid-strengthened Tungsten Alloys for Fusion Applications |
Author(s) |
Chase Hargrove, Trevor Marchhart, Nathan Reid, Xing Wang, Jean Paul Allain |
On-Site Speaker (Planned) |
Chase 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 |