| Scope |
Additive manufacturing (AM) has emerged as a transformative approach for producing materials for next-generation fission and fusion reactors, offering advantages such as design flexibility, reduced lead times, and supply chain resilience. The microstructure and properties of AM materials can vary considerably from those produced by conventional methods, which can lead to distinct performance, both beneficial and detrimental, under irradiation, corrosion, high temperature, and high stress conditions. AM materials can also unlock pathways for developing novel microstructures with enhanced irradiation tolerance. Rapid development of such materials is necessary to accelerate the deployment of new nuclear fission and fusion energy systems and extend the lifetime of light water reactors. Achieving this requires integrated efforts in advanced characterization, high throughput testing, and computational modeling of AM materials before, during, and after exposure to these environments. This symposium concentrates on structural and other non-fuel materials fabricated using AM; AM-fabricated fuels should be submitted to Accelerating Nuclear Fuels Research symposium.
Topics of interest include:
• Radiation effects in AM structural and other non-fuel materials
• Accelerated high throughput testing of AM materials
• Advanced characterization and properties testing techniques of AM materials, with an emphasis on combined effects testing and characterization (such as in-situ electron microscopy and coupled irradiation creep or irradiation-corrosion experiments)
• Computational modeling of AM defect structures under irradiation
• Comparing radiation response of materials manufactured by different routes, including melt-based AM, solid phase processing, and other non-traditional fabrication methods
• Use of AM for development of novel and irradiation-tolerant materials
• Recent advances towards commercial deployment of AM components |