Variation of Radiation Damage with Temperature in ODS Steel Studied by Triple Beam Irradiation and P

• 作 者: YUAN Da-qing FAN Ping WANG Xian-ping LONG Bin MA Hai-liang ZHANG Qiao-li ZUO Yi WEN A-li ZHENG Yong-nan KONG Xiang-shan ZHUANG Zhong TONG Zhen-feng FENG Wei LU Er-yang CAO Xing-zhong WANG Bao-yi WEI L
• 机 构: Department of Nuclear Physics,Institute of Solid State Physics,Chinese Academy of Sciences,Institute
• 出 处: Annual Report of China Institute of Atomic Energy
• 发表日期: 2016年00期
• 关键词: dispersed Triple synergistic cladding irradiation Hydrogen candidate advance str

The oxide dispersed strengthened(ODS)ferritic-martensitic steel is regarded as a candidate structural material for advance nuclear energy systems,which is especially used as cladding material for fast reactors.The radiation damage and synergistic effect of Hydrogen,Helium and displacement have been investigated in the temperature

The oxide dispersed strengthened (ODS) ferritic-martensitic steel is ide as a candidate structural material for advance nuclear energy systems, which is especially used as cladding material for fast reactors. The radiation damage and synergistic effect of Hydrogen, Helium and displacement have been investigated in the temperature