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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