先进核能系统用ODS钢的显微组织设计与调控研究进展

doi:10.11896/cldb.201901009

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Abstract Nuclear energy is a kind of important clean energy. The fourth-generation reactors and fusion reactors with improved safety and better economy are being developed internationally. Compared with the current commercial second and third-generation reactors, these advanced reactors will serve in a harsher environment with higher operation temperature and irradiation dose. The traditional zirconium alloy and stainless steel cannot meet the demanding service conditions in the future reactors. The development of new grade key structural materials with excellent comprehensive service performance has become one of the bottlenecks restricting the engineering application of advanced nuclear energy system. Ultra-fine nano-scale oxide particles with extremely high number density can be introduced into the steel matrix by advanced powder metallurgy methods such as mechanical alloying. Compared to the similar traditional melted steels, the oxide dispersion strengthened (ODS) steels show improved high temperature creep strength and anti-irradiation properties, thus can work at higher temperature. ODS steel has been identified as an important candidate material for cladding of fourth-generation reactors and blanket of future fusion reactors, which become an international research hot spot.
The superiority of ODS steel is based on its unique microstructure formed by advanced powder metallurgy process, i.e. submicron ultra-fine grain structure and homogeneous dispersed nano-oxide particles or clusters with an average particle size of only a few nanometers and high number density (above 10²³ m^-3). These oxide particles or clusters have extremely high thermal stability and irradiation stability, which can effectively strengthen the materials by dislocation pinning, thereby improving the high temperature strength and increasing the service temperature of the material. Besides, the interface formed between a large number of dispersed particles and the matrix can effectively capture the defects and bubbles caused by irradiation, and in consequence, significantly improve the resistance for irradiation induced swelling. Microstructure design and control to meet the service requirements is a core issue for the preparation of high-performance advanced materials, while the microstructure is obviously affec-ted by composition design, fabrication technology and process parameters. Although the research activities on ODS steels have become more and more active in recent years, some fundamental problems, such as the relationship between composition design, fabrication history and micro-nano-structure still need further exploration due to the complexity of the microstructure and preparation process of ODS steels.
This paper focuses on the basic core problems of the application of ODS steel for advanced nuclear energy systems, follows the thread of the relationship among the microstructure characteristics, composition design and preparation technology, and summarizes the stat-of-art global research outputs. It is expected to provide reference for the engineering application of the ODS steel in the advanced nuclear reactors.

Key words： ODS steel composition design microstructure stability reactor cladding fusion blanket radiation resistance

Published: 24 January 2019

CLC number:	TG142
	TB333

Fund:The work was supported by the National Magnetic Confinement Fusion Energy Research Project of China (2015GB121006).

About author:: Shuai Xu received her B.E. Degree in University of Science and Technology Beijing in 2014. She is a Ph.D. student in the School of Materials Science and Enginee-ring, University of Science and Technology Beijing under the supervision of Prof. Zhangjian Zhou. Her research interest is the trade-off between strength and toughness of oxide dispersion strengthened (ODS) steels.Zhangjian Zhou is currently a full professor in University of Science and Technology Beijing. He received B.E. and M.E. degree In petrology and mineralogy from China Geoscience University, in 1993 and 1996, and received Ph.D. degree in materials science from University of Science and Technology Beijing in 2007. He is Member of the Advisory Editorial Board of the Journal of Nuclear Materials and Member of International Advisory
Committees for FGM’S. His recent research interest is to design, synthesis and investigation of advanced materials application for the extreme environment, such as nuclear system.

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	XU Shuai
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Cite this article:

XU Shuai,CHEN Lingzhi,CAO Shuguang, et al. Research Progress on Microstructure Design and Control of ODS Steels Applied to Advanced Nuclear Energy Systems[J]. Materials Reports, 2019, 33(1): 78-89.

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http://www.mater-rep.com/EN/10.11896/cldb.201901009 OR http://www.mater-rep.com/EN/Y2019/V33/I1/78

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