Fusion materials research topics will include both structural and functional materials required for nuclear systems. This area covers such things as compilations of government reports and literature surveys. It also includes neutron irradiations, material characterization, development of engineered materials, advanced manufacturing applied to fusion systems, documentation of physical properties, safety analysis involving materials compatibility for both solids and liquids, corrosion and wear, liquid metal embrittlement, tritium permeation, joining processes, plasma surface interactions involving erosion, redeposition, wall conditioning, dust formation, waste handling and decommissioning.
It also includes development of new magnet materials including HTSC materials, their testing and documentation. The area also covers any challenges involving new breeder and neutron multiplier materials for both solid and liquid breeders and new shield materials.
Related News
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INFUSE FAQ Webinar – Dec. 4 at 3pm (EST)
Join the INFUSE team for an opportunity to learn more about the application process and an chance to ask questions. We invite you to view the Frequently Asked Questions section of the website prior to submitting or asking questions. You are also welcome to submit questions for the team before the event: https://forms.office.com/g/AFdaREfDQf Zoom Link
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DOE announces $134 million to advance fusion
On September 10, 2025 the U.S. Department of Energy announced funding for two program: Fusion Innovation Research Engine (FIRE) and Innovation Network for Fusion Energy (INFUSE). Read full announcement here.
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Registration for FY26 Workshop Open
Join us at the Oak Ridge National Laboratory for the FY2026 INFUSE workshop! On the first day, optional tours will be given of several of the state-of-the-art facilities at ORNL. On day two and three, participants will participate in poster discussions, panels, and collaborations with industry, national labs, and universities.
Related Awards
Characterization and Tritium Breeding Ratio Measurement of Li-6-enriched Lithium Samples After Thermal Neutron Irradiation
INFUSE 2025 - September 10, 2025 | Kyoto Fusioneering America Ltd. | Idaho National Laboratory (INL)
Development of Fusion-Grade Lithium Material Specifications
INFUSE 2025 - September 10, 2025 | Molten Salt Solutions | Los Alamos National Laboratory (LANL)
Mechanical Characterization of Neutron Irradiated Tungsten
INFUSE 2025 - September 10, 2025 | Commonwealth Fusion Systems | Oak Ridge National Laboratory (ORNL)
Evaluating the impact of lead-lithium purity on tritium transport
INFUSE 2025 - September 10, 2025 | EX-Fusion America, Inc | Idaho National Laboratory (INL)
High magnetic field transport testing and microstructure characterization for development of high performance REBCO wires for fusion
INFUSE 2025 - September 10, 2025 | SuperPower, Inc. | FSU
Experimental assessment of cold spray technology for corrosion protection of components facing liquid Pb-Li and FLiBe breeding blankets
INFUSE 2025 - September 10, 2025 | Westinghouse Electric Company, LLC | Virginia Polytechnic Institute and State University