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.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4933-0
PROCEEDINGS PAPER
Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System Available to Purchase
Zhangjian Zhou,
Zhangjian Zhou
University of Science and Technology Beijing, Beijing, China
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Ming Li,
Ming Li
University of Science and Technology Beijing, Beijing, China
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Lu Liao,
Lu Liao
University of Science and Technology Beijing, Beijing, China
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Pei He,
Pei He
University of Science and Technology Beijing, Beijing, China
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Yingli Xu
Yingli Xu
University of Science and Technology Beijing, Beijing, China
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Zhangjian Zhou
University of Science and Technology Beijing, Beijing, China
Ming Li
University of Science and Technology Beijing, Beijing, China
Lu Liao
University of Science and Technology Beijing, Beijing, China
Pei He
University of Science and Technology Beijing, Beijing, China
Yingli Xu
University of Science and Technology Beijing, Beijing, China
Paper No:
ICONE18-29854, pp. 219-222; 4 pages
Published Online:
April 8, 2011
Citation
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
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