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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Meeting Materials Challenges for the Future of Fusion Energy
Presentation Title W-Cr Composite with Improved Fracture Toughness for Plasma-Facing Material: Fabrication and Mechanical Properties Characterization
Author(s) Sungmin Lee, Jeongseok Kim, Nojun Kwak, Heung Nam Han
On-Site Speaker (Planned) Sungmin Lee
Abstract Scope Tungsten is considered as the most promising candidate materials for plasma-facing component (PFC) in nuclear fusion reactor due to its high melting point, high hardness and low sputter yield. However, tungsten shows low fracture toughness at relatively low temperature, which makes tungsten vulnerable to brittle fracture in the vicinity of the cooling pipe in the PFC. In this research, tungsten’s brittleness was overcome by ductile-phase toughening effect in composite. For the toughening effect, W-Cr powder with core-shell structure was produced by high energy milling and the eventual unique composite structure with W particle covered with Cr network was formed with SPS. Its fracture toughness was assessed by ASTM E399 standard and fractography observation displayed microstructural evidences of fracture toughness improvement. Furthermore, other properties were characterized at various temperatures to assess its validity as plasma-facing materials.
Proceedings Inclusion? Planned:
Keywords Mechanical Properties, Composites, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Carbon Foam to SiC Conversion Technology for Flow Channel Inserts
A Machine Learned Potential for H Behavior in Dispersion-Strengthened W
Additive Manufacturing via Directed Energy Deposition of WTaCrV and WTaHfCrV Refractory High Entropy Alloys for Plasma Facing Components
Advancing the Scalable Fabrication of Oxide Dispersion Strengthened (ODS) Steel Plates
Annealing of Neutron Irradiated Tungsten to Assess the Stability of Irradiation Induced Transmutant Solute Clusters
ARPA-E CHADWICK Fusion Materials Program Overview
Assessment of Additive Manufacturing Techniques for Obtaining Ferritic/Martensitic ODS
Benchmark Study of Three-Element Medium Entropy Alloy WTaV for Fusion Reactors Plasma-Facing Applications
Characterisation of Oxide Dispersion Strengthened Steels for Nuclear Fusion Application
Current R&Ds on Advanced Breeding Functional Materials for JA DEMO Activities
Defect Phase Diagrams and Structure-Property Relationships for Screw Dislocations of Tungsten in the Presence of Hydrogen Studied by Atomistic Simulations
Demystify Radiation-Enhanced Hydrogen Isotope Diffusion
Design Strategy of PWHT-Free Reduced-Activation Bainitic Steel for Vacuum Vessel Components in Fusion Reactors
Development of Industrially Scalable High-Temperature Steels for Fusion Applications
Development of Machine Learned Interatomic Potentials for Modeling Transmutation Products in Fusion First Wall Materials
Development of Machine Learning Potential to Study Tritium Behavior in V-Alloy Blanket with Liquid Lithium Breeder
Development of SiC Composite Blanket for Fusion
Effect of Transmutation Products on Point Defect Energies in Tungsten From First-Principles and Machine Learning
Effects Of Ion Irradiation on Microstructure and Micromechanical Properties of a Ductile-Phase-Toughened Tungsten Heavy Alloy
Emerging Alloy Materials for Fusion Power
Enhanced Radiation Resistance of W-Based HEA Under Helium-Ion Irradiation Conditions
Evolution of He Bubble Morphology During In Situ Heating of Plasma Exposed Tungsten and Tungsten Alloys
Exploration of Ferrous Alloys as Radiation Damage Resistant Materials for Fusion
First Principles Calculations of Fusion-Relevant Transmutation Defects in SiC
Fracture Toughness of F82H Steel after Neutron Irradiation to ~70 dpa at 400°C and 500°C
Functional Coating Development for Fusion Reactors
Hierarchical Multiscale Modeling Framework to Predict Surface Morphology of Plasma Facing Components
High Throughput Self-Ion Irradiation and Characterization of Pure Tungsten
Identification of Transmutation Products in Irradiated Tungsten
Impact Dynamics of High-Velocity Tungsten Dust in Fusion Reactors: A Molecular Dynamics Study
Impact of Soret Effect on Hydrogen and Helium Retention in PFC Tungsten Under ELM-Like Conditions
Improved Damage Detection Around Grain Boundaries in Tungsten from Atomistic Calculations
In Situ Micropillar Compression Study of Ultra-Fine-Grained Tungsten at Elevated Temperature
Innovative Lithium-Based Tritium Breeder Material with Promising Microstructure
Investigation Of Microstructure and Mechanical Properties in Cost-Effective Thermomechanically Processed Nanostructured Ferritic Alloys
Irradiation Experiments for Fusion Blanket Materials
Laser Additive Manufacturing of PFCs for Nuclear Fusion: Studying the Influence of Tungsten Deposition on RAFM Steel Using Multimodal Synchrotron Imaging
Love & Marriage: Point Defect Coexistence in Nanostructured Tungsten
Material Characterization of Lateral Transmutation Gas Gradients in Triple-Ion Irradiated F82H-IEA
Micromechanical Investigation of WC for Shielding Applications in Compact Fusion Devices
Microstructural Changes in Ion and Neutron Irradiated REBCO-Based Magnet Materials for Fusion
Microstructure Modification of Tungsten by Alloying, Dispersion Strengthening, and Thermomechanical Processing for Fusion Energy Applications
Modeling of Dislocation Loop Evolution in Iron Through Kinetic Monte Carlo
Phase Field Fracture Modeling to Investigate the Integrity of Lithium Aluminate Pellets Used for Tritium Breeding
Physics-Based Evaluation of General Fusion Facility Concepts for a Prototypical Neutron Fusion Source
Predicting High-Dose Irradiation Damage Using Statistical Surrogate Models of Cascade Defect Production
Processing and Irradiation Damage in Novel Tritium Breeding Ceramics with High Lithium Content
Progress and Issues of R&D on Fusion DEMO Structural Materials in Japan
Radiation Effects Challenges in High-Performance Materials
RAFM Welding with In-Situ Thermal Processing for Simplified First Wall Fabrication
Refractory Alloy Processing Challenges for Next-Generation Energy Systems
Responses of Dispersion-Strengthened Tungsten to High Heat Flux and High Fluence Helium Irradiation
Scale-Up of Advanced Castable Nanostructured Alloys for Fusion First-Wall/Blanket Applications
Shrinking Pains – Materials Challenges in a More Compact Fusion Device
Simulating Plasma-Surface Interactions with Deuterium Beams Experiments: Effect of Tungsten Oxidation
Spark Plasma Sintering of Dispersion-Strengthened Tungsten for Fusion Applications
Synergetic Effects of Hydrogen on Cavity Formation in Candidate Fusion Blanket Materials: Past and Future Studies
Synergistic Study of Neutron Irradiation and Hydrogen Exposure on Tungsten
Temperature Dependent Thermal-Mechanical Properties of Plasma-Facing Materials - W, SiC, and Fe-Cr Alloy
The Effect of Ion Irradiation Conditions on the Damage Morphology of a Tungsten Heavy Alloy
The role of AI in Advancing Materials Development and Testing for Fusion Energy Deployment
The Role of Hydrogen Co-Injection on the Cavity Microstructure of Triple Ion Irradiated F82H-IEA
Thermal Permeation of Tungsten Wafers
Thermomechanical Processing of Tungsten and its Alloys for Fusion Energy Applications
Toward Understanding of the Response of SiC to Fusion Neutron Irradiation
Transmutations in Advanced Nuclear Ceramics Exposed to Fusion Environments
Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Tungsten Boride Shielding Material for Fusion Reactors
Ultra High Temperature Ceramics for Fusion Energy Applications
Understanding the Role of Short-Range Order on Defect Thermodynamics in Tungsten Alloys
W-Cr Composite with Improved Fracture Toughness for Plasma-Facing Material: Fabrication and Mechanical Properties Characterization
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