title: Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation.
abstract: The world eagerly needs cleanly-generated electricity in the future. Fusion reactor is one of the most ideal energy resources to defeat the environmental degradation caused by the consumption of traditional fossil energy. To meet the design requirements of fusion reactor, the development of the structural materials which can sustain the elevated temperature, high helium concentration and extreme radiation environments is the biggest challenge for the entire material society. Oxide dispersion strengthened steel is one of the most popular candidate materials for the first wall/blanket applications in fusion reactor. In this paper, we evaluate the radiation tolerance of a 9Cr ODS steel developed in China. Compared with Ferritic/Martensitic steel, this ODS steel demonstrated a significantly higher swelling resistance under ion irradiation at 460 °C to 188 displacements per atom. The role of oxides and grain boundaries on void swelling has been explored. The results indicated that the distribution of higher density and finer size of nano oxides will lead a better swelling resistance for ODS alloy. The original pyrochlore-structured Y2Ti2O7particles dissolved gradually while fine Y-Ti-O nano clusters reprecipitated in the matrix during irradiation. The enhanced radiation tolerance is attributed to the reduced oxide size and the increased oxide density.
authors.affiliation: Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education), School of Materials Science and Engineering, Northeastern University, Shenyang 118109, Liaoning, China.|Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI 48109, United States.
authors.forename: Chenyang
authors.initials: C
authors.lastname: Lu
authors.affiliation: Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education), School of Materials Science and Engineering, Northeastern University, Shenyang 118109, Liaoning, China.
authors.forename: Zheng
authors.initials: Z
authors.lastname: Lu
authors.affiliation: China Nuclear Power Technology Research Institute, China General Nuclear Power Corporation, Shenzhen, Guangdong 518000, China.
authors.forename: Xu
authors.initials: X
authors.lastname: Wang
authors.affiliation: Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education), School of Materials Science and Engineering, Northeastern University, Shenyang 118109, Liaoning, China.
authors.forename: Rui
authors.initials: R
authors.lastname: Xie
authors.affiliation: Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education), School of Materials Science and Engineering, Northeastern University, Shenyang 118109, Liaoning, China.
authors.forename: Zhengyuan
authors.initials: Z
authors.lastname: Li
authors.affiliation: Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI 48109, United States.
authors.forename: Michael
authors.initials: M
authors.lastname: Higgins
authors.affiliation: Key Laboratory for Anisotropy and Texture of Materials (Ministry of Education), School of Materials Science and Engineering, Northeastern University, Shenyang 118109, Liaoning, China.
authors.forename: Chunming
authors.initials: C
authors.lastname: Liu
authors.affiliation: Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI 48109, United States.
authors.forename: Fei
authors.initials: F
authors.lastname: Gao
authors.affiliation: Department of Nuclear Engineering and Radiological Science, University of Michigan, Ann Arbor, MI 48109, United States.|Department of Materials Science and Engineering, University of Michigan, Ann Arbor, MI 48109, United States.
authors.forename: Lumin
authors.initials: L
authors.lastname: Wang