Evolution of radiation-induced segregation atgrain boundaries in AL-6XN stainless steels iradiated b

• 作 者: Zheng Zhongcheng Guo Liping Zhang Weiping Sheng Zhenyu Tang Rui
• 机 构: Hubei Nuclear Solid Physics Key Laboratory,Key Laboratory of Artificial Micro-and Nano-structures of
• 出 处: 第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
• 发表日期: 2016年3期
• 关键词: Supercritical water-cooled reactor Austenitic stainless steels Radiation-induced

　　Hydrogen radiation-induced segregation(RIS)in AL-6XN stainless steels,which are one of the candidate structure materials for supercritical water-cooled reactor,has been investigated by transmission electron microscopy(TEM)with energy-dispersive X-ray spectroscopy.Specimens were irradiated with 50 keV H+ions from 0.5 to 5 dpa at 290℃ and 380℃.Significant RIS in irradiated specimens was found,Cr was depleted while Ni,Si and P were enriched at grain boundaries and it varies with the temperature and irradiation dose.The effects of hydrogen and elevated temperature on the segregation evolution were studied and the possible mechanism were discussed in this paper.