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Meeting MS&T24: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
Presentation Title Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Author(s) Bai Cui, Yongchul Yoo, Xiang Zhang, Fei Wang, Xin Chen, Xing-Zhong Li, Michael Nastasi
On-Site Speaker (Planned) Bai Cui
Abstract Scope W-based WTaVCr refractory high entropy alloys (RHEA) may be promising candidate materials for plasma facing components in the first wall and diverter in fusion reactors. This alloy is developed by a powder metallurgy process combining mechanical alloying and spark plasma sintering (SPS), as well as laser powder bed fusion (LPBF). The samples contained two phases, in which the matrix is RHEA with a body-centered cubic structure, while the oxide phase was most likely Ta2VO6 and TaVO4 through a combined analysis of X-ray diffraction, energy-dispersive spectroscopy, and selected area electron diffraction. The higher oxygen affinity of Ta and V may explain the preferential formation of their oxide phases based on thermodynamic calculations. WTaVCr RHEA showed a peak compressive strength of 2997 MPa at room temperature and much higher micro- and nano-hardness than W and other RHEAs in the literature. Their high Rockwell hardness can be retained to at least 1000C.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization Capabilities of Nuclear Materials via NSUF
Advanced In-Situ Strain Mapping for Zr Oxidation by 4D-SPED
An In-Situ Transmission Electron Microscopy Study on the Synergistic Effects of Heating and Biasing of AlGaN/GaN High Electron Mobility Transistors
Atomic-Scale Hidden Point-Defect Complexes Induce Ultrahigh Irradiation Hardening in BCC Metals
Characterization of Aluminum Under Shock: Defects, Grain Orientation, and Phase Stability
Characterization of Radiation Damage in Nanocrystalline Ni- and Fe-Based Oxide Dispersion-Strengthened Alloys
Deciphering and Visualizing Helium Accumulation and Dynamics in Materials via In-Situ Characterization
Deployment and Testing of a Fiber-Based Instrument for In-Reactor Thermal Property Measurements at MIT Research Reactor
Determination of Molten Salt Thermal Conductivity Using Laser Flash Technique
Dynamics of Radiation Defect Accumulation in Non-Metallic Materials
Formation and Recover of Dislocations Under Deformation and/or Irradiation of Elemental Tantalum, a Step Toward Understanding Complex BCC Alloys.
Impact of Amorphous Pockets on Displacement Damage Evolution in Crystalline Silicon
Influence of Defects Length-Scale on Nuclear Graphite Properties
Interactions Between Radiation-Induced Defects and Shock in Al 1100
Investigation of Helium Bubble Formation at Tungsten-Dispersoid Interfaces in Dispersion-Strengthened Tungsten Alloys
L-1: Application of Laboratory-Based Photoelectron Spectroscopy with Hard and Soft X-Rays to Nuclear Forensics Characterization of Uranium Dioxide Fuel
L-2: Effect of Swift Heavy Ion Irradiation on Silicon Carbide
Localized Crystallization of Zr Following Heavy Ion Irradiation of HfNbTaZr MPEA
Machine Learning and Molecular Dynamics-Coupled X-Ray Absorption Spectroscopy for Disordered Multicomponent Systems
Microstructural and Chemical Evolution Studies of U-10Zr Metallic Fuel and HT9 Cladding from Fast Flux Test Facility
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Nanoscale Redistribution of Lithium in Neutron Irradiated LiAlO2
Neutron-Induced Reversible Nanostructuring of GeSe2
Quantitative Phase Characterization of Nuclear Cements and Concretes Using Non-Destructive 3D Automated Mineralogy and Enhanced Deep-Learning Reconstruction via X-ray Microscopy
Real-time Neutron Diffraction to Support Interpretation of DSC Results on Zr-2.5Nb for Reactor Pressure Tubes
Strong Dependence of 2D Material Radiation Tolerance on the Composition of the 2D Material and Its Surrounding Environment
Structural Characterization of Ultra-High Temperature Ceramics in Three Dimensions for Statistical and Physics-Based Modeling
Superimposed Effects of Texture and Grain Shape Anisotropy on Biaxial Creep Behavior of Nb-Modified Zircaloy-4 Cladding
Synthesis and Irradiation of Uranium Carbide and Nitride for TRISO Development
Thermophysical Characterisation of Zirconium-Based Nuclear Materials
Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Understanding Irradiation Assisted Hydrogen Embrittlement Using In Situ Coherent X-Ray Imaging
Understanding the Mechanism of Fission Gas Re-Solution and Blistering in UMo Fuel via Atomistic Modelling
Understanding the Surface and Near Surface via Nanomechanical Mapping

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