About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| 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 >10^21 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? |
Planned: |
| Keywords |
Characterization, Powder Materials, Shaping and Forming |