|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Nanostructured Materials for Nuclear Applications
||Microstructure and Strengthening Mechanism of Austenitic ODS Steels for High-Temperature Nuclear Applications
||Yinbin Miao, Kun Mo, Zhangjian Zhou, Xiang Liu, Kuan-Che Lan, Guangming Zhang, Jun-Sang Park, Jonathan Almer, James F Stubbins
|On-Site Speaker (Planned)
Austenitic ODS steels are promising candidates for structural materials in prospective advanced nuclear systems. A series of austenitic ODS steels, including ODS 304, ODS 310, ODS 316, and ODS 316Hf, were investigated by a coordinated combination of advanced characterization techniques. Phase identification of the oxide nanoparticles was performed based on synchrotron diffraction and analytic STEM results. Y-Ti-O enriched phases were found to dominate the ultra-fine particles (<10 nm), while Y-Al-O enriched particles may exist in the presence of Al addition. The size distribution of the oxide nanoparticles was measured by both synchrotron small-angle scattering and TEM observations. In-situ synchrotron tensile investigation was used to examine the load-partitioning phenomenon contributed by the oxide nanoparticles as well as the dislocation density and texture evolution during uniaxial tensile straining. Various types of austenitic ODS steels were compared to provide guidance to the development of future practical austenitic ODS steels for nuclear applications.
||Planned: A print-only volume