Acta Metallurgica Sinica (English Letters) ›› 2017, Vol. 30 ›› Issue (1): 89-96.DOI: 10.1007/s40195-016-0490-2

Special Issue: 2017年钢铁材料专辑

• Orginal Article • Previous Articles    

Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions

Zhong-Cheng Zheng1,Yan-Xia Yu1,Wei-Ping Zhang1,Zhen-Yu Shen1,Feng-Feng Luo1,2,Li-Ping Guo1(),Yao-Yao Ren3,Rui Tang4   

  1. 1.Hubei Nuclear Solid Physics Key Laboratory, Key Laboratory of Artificial Micro- and Nano-structures of Ministry of Education and School of Physics and Technology Wuhan University Wuhan China
    2.Institute of Applied Physics Jiangxi Academy of Science Nanchang China
    3.Center for Electron Microscopy Wuhan University Wuhan China
    4.Science and Technology on Reactor Fuel and Materials Laboratory Nuclear Power Institute of China Chengdu China
  • Received:2016-03-14 Online:2017-02-16 Published:2017-02-16

Abstract:

AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2+ ions at 290 and 380 °C. Microstructures were characterized by transmission electron microscopy (TEM). Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 <111> type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 °C. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.

Key words: Supercritical water-cooled reactor, Austenitic stainless steelsIon irradiation, Dislocation loops, Hydrogen