Development of cladding materials which can work at high temperature is crucial to realize highly efficient and high-burnup operation of Generation IV nuclear energy systems. Oxide dispersion strengthened (ODS) steels are the most promising class of materials with a potential to be used at elevated temperature under severe corrosion and strong neutron exposure environment. ODS ferritic steels with Cr content of 12–18% were designed and fabricated through the mechanical alloying (MA) route. The characterization of ODS ferritic steels were conducted for evaluation their potential applications for advanced nuclear energy system. Mechanical properties were measured at room temperature and high temperature. High-temperature (700 °C–1000 °C) oxidation resistance were carried out using a muffle. Microstructures of the oxidation layer were observed and compared.
- Nuclear Engineering Division
Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System
- Views Icon Views
- Share Icon Share
- Search Site
Zhou, Z, Li, M, Liao, L, He, P, & Xu, Y. "Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 219-222. ASME. https://doi.org/10.1115/ICONE18-29854
Download citation file: