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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 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

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

An Innovative Additive Manufacturing Route for Metal Matrix Composites for Nuclear Applications
Characterization of Defects Generated from Thermal Stresses in SiC/SiC Composites
Characterization of the Effects of Intermediate Temperature Neutron Irradiation on Model Fe-Cr Alloys
Correlating Heterogeneous Pore Distribution with Stochastic Fracture in the Pyrocarbon Buffer Layer in TRISO Fuel Particles
Development and Additive Manufacturing of ODS IN-718 Alloys for Nuclear Applications
Development and Evaluation of Dual-purpose Coating to SiC/SiC Composite Accident-tolerant Fuel Cladding for Light Water Reactors
Development of SiCf/SiC Composite Materials for Fusion Applications
Effect of Copper Fiber in RAFM Steel Composite on Improving the Thermal Conductivity
Effect of Hot Rolling and High Temperature Annealing on the Microstructure and Mechanical Properties of Hot-rolled 90W7Ni3Fe WHA
Effect of Interfacial Features on the Strengthening Behavior of B4C/Al Composites
ENHANCED Shield: A Critical Materials Technology Enabling Compact Superconducting Tokamaks
Ion Beam Synthesis of Nano-Oxides in FeCr: Towards an Understanding of Precipitation in Oxide Dispersion Strengthened Steels
Irradiation Effects in the Composite Phases of Graphite and Carbon-Based Materials
Is there Residual Stress in Tungsten Fiber Reinforced Tungsten Composites
Mechanistic Understanding of Hydrothermal Corrosion of SiC Under Irradiation
Microstructure and Mechanical Behavior of Cr Coatings for Mitigating Hydrothermal Corrosion of SiC-SiCf Fuel Cladding
Microstructure and Thermophysical Property Characterization of U-ZrHx Fuel Fabricated by Powder Metallurgy
Next-generation Nuclear Grade Composite Components
Nuclear Graphite as a Core Composite Material
Oxidation Effects on the Microstructure of Nuclear Graphite
Oxidation Response of Irradiated and Unirradiated TRISO Fuel
Progress in the Development of Tungsten Fibre-reinforced Copper Composites for Heat Sink Applications in Plasma-facing Components
Recent Progress in the Development of Tungsten Fibre-reinforced Tungsten Composite
Role and Structure of HTGR Matrix Material
Ruthenium and Silver Diffusion in Nuclear Graphite
Status Update on Framatome PROtect ATF Solutions: Cr-coated M5Framatome and SiCf/SiC Cladding Designs
Stress Rupture of SiC/SiC Composite Tubes Under High-temperature Steam: Implications for Resistance to Light Water Reactor Accident
Thermal Properties of Dispersoid-strengthened Tungsten Alloys for Fusion Applications
W2C-reinforced Tungsten: A Promising Candidate for EU DEMO Divertor Material

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