中国物理B ›› 2021, Vol. 30 ›› Issue (8): 86103-086103.doi: 10.1088/1674-1056/ac0a64

所属专题： SPECIAL TOPIC — Ion beam modification of materials and applications

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Microstructure evolution of T91 steel after heavy ion irradiation at 550 ℃

Ligang Song(宋力刚)1, Bo Huang(黄波)1, Jianghua Li(李江华)2, Xianfeng Ma(马显锋)1,†, Yang Li(李阳)3,4,‡, Zehua Fang(方泽华)1, Min Liu(刘敏)1, Jishen Jiang(蒋季伸)1, and Yanying Hu(胡琰莹)1   

  1. 1 Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 519082, China;
    2 State Key Laboratory of Nonlinear Mechanics(LNM), Institute of Mechanics, Chinese Academy of Sciences, Beijing 100190, China;
    3 DEN-Service de Recherches Métallurgiques Appliquées, CEA, Université Paris-Saclay, Gif-sur-Yvette 91191, France;
    4 Department of Mechanical and Aerospace Engineering, University of California Los Angeles, Los Angeles, CA 90095, USA
  • 收稿日期:2021-03-30 修回日期:2021-06-05 接受日期:2021-06-11 出版日期:2021-07-16 发布日期:2021-08-02
  • 通讯作者: Xianfeng Ma, Yang Li E-mail:maxf6@mail.sysu.edu.cn;yang.li@cea.fr
  • 基金资助:
    Project supported by Guangdong Major Project of Basic and Applied Basic Research (Grant No. 2019B030302011), the National Natural Science Foundation of China (Grant Nos. U2032143, 11902370, and 52005523), the International Science and Technology Cooperation Program of Guangdong Province, China (Grant No. 2019A050510022), the China Postdoctoral Science Foundation (Grant Nos. 2019M653173 and 2019TQ0374), and the Heavy Ion Research Facility of Lanzhou (HIRFL).

Microstructure evolution of T91 steel after heavy ion irradiation at 550 ℃

Ligang Song(宋力刚)1, Bo Huang(黄波)1, Jianghua Li(李江华)2, Xianfeng Ma(马显锋)1,†, Yang Li(李阳)3,4,‡, Zehua Fang(方泽华)1, Min Liu(刘敏)1, Jishen Jiang(蒋季伸)1, and Yanying Hu(胡琰莹)1   

  1. 1 Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 519082, China;
    2 State Key Laboratory of Nonlinear Mechanics(LNM), Institute of Mechanics, Chinese Academy of Sciences, Beijing 100190, China;
    3 DEN-Service de Recherches Métallurgiques Appliquées, CEA, Université Paris-Saclay, Gif-sur-Yvette 91191, France;
    4 Department of Mechanical and Aerospace Engineering, University of California Los Angeles, Los Angeles, CA 90095, USA
  • Received:2021-03-30 Revised:2021-06-05 Accepted:2021-06-11 Online:2021-07-16 Published:2021-08-02
  • Contact: Xianfeng Ma, Yang Li E-mail:maxf6@mail.sysu.edu.cn;yang.li@cea.fr
  • Supported by:
    Project supported by Guangdong Major Project of Basic and Applied Basic Research (Grant No. 2019B030302011), the National Natural Science Foundation of China (Grant Nos. U2032143, 11902370, and 52005523), the International Science and Technology Cooperation Program of Guangdong Province, China (Grant No. 2019A050510022), the China Postdoctoral Science Foundation (Grant Nos. 2019M653173 and 2019TQ0374), and the Heavy Ion Research Facility of Lanzhou (HIRFL).

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摘要： Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the Generation IV nuclear technologies. In this study, a widely-used ferritic/martensitic steel, T91 steel, was irradiated by 196-MeV Kr+ ions at 550 ℃. To reveal the irradiation mechanism, the microstructure evolution of irradiated T91 steel was studied in details by transmission electron microscope (TEM). With increasing dose, the defects gradually changed from black dots to dislocation loops, and further to form dislocation walls near grain boundaries due to the production of a large number of dislocations. When many dislocation loops of primary a0/2<111> type with high migration interacted with other defects or carbon atoms, it led to the production of dislocation segments and other dislocation loops of a0<100> type. Lots of defects accumulated near grain boundaries in the irradiated area, especially in the high-dose area. The grain boundaries of martensite laths acted as important sinks of irradiation defects in T91. Elevated temperature facilitated the migration of defects, leading to the accumulation of defects near the grain boundaries of martensite laths.

关键词: T91 steel, high energy Kr ions irradiation, irradiation defects, transmission electron microscope (TEM)

Abstract: Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the Generation IV nuclear technologies. In this study, a widely-used ferritic/martensitic steel, T91 steel, was irradiated by 196-MeV Kr+ ions at 550 ℃. To reveal the irradiation mechanism, the microstructure evolution of irradiated T91 steel was studied in details by transmission electron microscope (TEM). With increasing dose, the defects gradually changed from black dots to dislocation loops, and further to form dislocation walls near grain boundaries due to the production of a large number of dislocations. When many dislocation loops of primary a0/2<111> type with high migration interacted with other defects or carbon atoms, it led to the production of dislocation segments and other dislocation loops of a0<100> type. Lots of defects accumulated near grain boundaries in the irradiated area, especially in the high-dose area. The grain boundaries of martensite laths acted as important sinks of irradiation defects in T91. Elevated temperature facilitated the migration of defects, leading to the accumulation of defects near the grain boundaries of martensite laths.

Key words: T91 steel, high energy Kr ions irradiation, irradiation defects, transmission electron microscope (TEM)

中图分类号:  (Radiation effects on specific materials)

  • 61.82.-d
61.72.U- (Doping and impurity implantation) 61.72.-y (Defects and impurities in crystals; microstructure) 07.78.+s (Electron, positron, and ion microscopes; electron diffractometers)