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About this Symposium

Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Developments in Advanced Nuclear Structural Materials
Sponsorship
Organizer(s) Rongjie Song, Idaho National Laboratory
Assel Aitkaliyeva, University of Florida
Bai Cui, University of Nebraska Lincoln
Fanny Balbaud, Cea
Caleb Massey, Oak Ridge National Laboratory
Caleb Clement, Westinghouse Electric Company
Scope This symposium will highlight recent advances in the design, development, and performance evaluation of new nuclear structural materials for fission and fusion reactors. As nuclear energy remains essential to clean energy production, there is growing need for materials that can withstand extreme environments, including high radiation doses, high temperatures, mechanical stress and corrosive conditions. The symposium will emphasize innovative alloy development and advanced manufacturing approaches that enable improved safety, efficiency, and longevity of both current and advanced reactor systems.

Topics of interest include, but are not limited to:

• Design, development and qualification of new alloys and advanced materials.
• Advanced manufacturing and processing techniques (e.g., LPBF, DED, PM-HIP, cold spray, or high-throughput fabrication, etc.).
• High-temperature, corrosion- and stress-tolerant materials designed for extended service life.
• Integrated design-process-performance relationships that link fabrication innovations to material behavior.
• Advanced coatings and surface modification for improved corrosion and wear resistance.
• Performance of new materials under separate effects experiments (irradiation, temperature, stress, or corrosion).

This symposium focuses on new structural material development and performance arising from alloy design and advanced processing.

− Submissions centered on combined coupled extreme environment effects, or experimental technique development should be directed to the “Interrelated Extremes in Materials Degradation for Nuclear Environments” symposium.
− Submissions primarily addressing welding, repair, or joining methodologies for fusion reactors should be submitted to “Special Topics” symposium.
− Submissions centered on carbon and composite-based materials should be submitted to other relevant symposia.

Abstracts Due 07/01/2026
Proceedings Plan Undecided

PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

No additional information can be displayed at this time.


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