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