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Meeting Materials in Nuclear Energy Systems (MiNES) 2025
Symposium Materials in Nuclear Energy Systems (MiNES) 2025
Presentation Title Radiation Resistance of Nanostructured Ferritic Alloys With Tailored Grain Boundary Characteristics Produced via Various Methods
Author(s) Eda Aydogan, Dalong Zhang, Xiang Wang, Jens Darsell, Xiao Li, Mark Rhodes, Kayla Yano, Karen Kruska, Tingkun Liu, Aishani Sharma, Lin Shao, Zhihan Hu, Stuart Maloy, Iver Anderson
On-Site Speaker (Planned) Eda Aydogan
Abstract Scope Nanostructured ferritic alloys, having ultra-fine grain structure and high concentration of nano-size (~2-5 nm) oxide particles are considered for structural components in advanced nuclear reactors due to their excellent irradiation resistance, high strength and resistance to oxidation/corrosion under extreme conditions of temperature and pressure. Here, we have developed ferrous nanostructured alloys produced by two different routes: (i) shear-deformation based friction extrusion of gas atomized reactive synthesis powders without ball milling (ii) conventional powder metallurgy processing including ball milling followed by heat treatments to tailor the nano-oxide concentration as well as the grain boundary characteristics. Advanced microstructural characterization using transmission electron microscopy and atom probe tomography has indicated a nano-oxide density of >1021 m-3 in both alloys. Comparative thermal stability studies up to 800 °C and high dose heavy ion irradiation studies at 450 °C have been conducted on these alloys.
Proceedings Inclusion? Undecided

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