About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
O-32: Fabrication and Characterization of Oxide Dispersion Strengthened Nickel Alloys for Advanced Molten Salt Reactor Components |
Author(s) |
Jaeyoon Bae, Sumin Lee, Juwook Lee, Sanghoon Noh |
On-Site Speaker (Planned) |
Jaeyoon Bae |
Abstract Scope |
ODS alloy has been developed as most prospective structural material for next-generation nuclear systems because of its excellent high strength and irradiation resistance. Finely dispersed nano-oxide particles with a high number density in homogeneous grains can be very attractive to achieve superior mechanical properties at high temperatures, and these favorable microstructures can be significantly changed with various fabrication process parameters. A preliminary work has been performed to develop ODS Ni alloys as structural materials for the MSR components. Pre-mixed powders with Y2O3 were mechanically alloyed for various milling parameters using a planetary ball-mill apparatus. Uniaxial hot pressing was employed to consolidate the milled powders instantly. Microstructural observation indicated that the refinement and homogeneity of grain structures were considerably increased and these led excellent mechanical properties at room and elevated temperatures. Results suggest a promising applicability of Ni-Mo ODS alloy for the MSR components with higher reliability and economic competitiveness. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, High-Temperature Materials, Mechanical Properties |