Microstructure and hardening effect of pure tungsten and ZrO2 strengthened tungsten under carbon ion irradiation at 700℃  

作　　者：Chun-Yang Luo Bo Cui Liu-Jie Xu Le Zong Chuan Xu En-Gang Fu Xiao-Song Zhou Xing-Gui Long Shu-Ming Peng Shi-Zhong Wei Hua-Hai Shen 罗春阳;崔博;徐流杰;宗乐;徐川;付恩刚;周晓松;龙兴贵;彭述明;魏世忠;申华海(Institute of Nuclear Physics and Chemistry,China Academy of Engineering Physics,Mianyang 621900,China;National&Local Joint Engineering Research Center for Abrasion Control and Molding of Metal Materials,Henan University of Science and Technology,Luoyang 471003,China;Institute of Heavy Ion Research,Peking University,Beijing 100871,China)

机构地区：[1]Institute of Nuclear Physics and Chemistry,China Academy of Engineering Physics,Mianyang 621900,China [2]National&Local Joint Engineering Research Center for Abrasion Control and Molding of Metal Materials,Henan University of Science and Technology,Luoyang 471003,China [3]Institute of Heavy Ion Research,Peking University,Beijing 100871,China

出　　处：《Chinese Physics B》2022年第9期404-411,共8页中国物理B（英文版）

基　　金：Project supported by the President's Foundation of the ChinaAcademy of Engineering Physics(Grant No.YZJJLX2018003);the National Natural Science Foundation of China(Grant Nos.U2004180 and 12105261);the Program for Changjiang Scholars and Innovative Research Team in Universities,China(Grant No.IRT1234).

摘　　要：Microstructure evolution and hardening effect of pure tungsten and W-1.5%ZrO_(2) alloy under carbon ion irradiation are investigated by using transmission electron microscopy and nano-indentation.Carbon ion irradiation is performed at 700℃ with irradiation damages ranging from 0.25 dpa to 2.0 dpa.The results show that the irradiation defect clusters are mainly in the form of dislocation loop.The size and density of dislocation loops increase with irradiation damages intensifying.The W-1.5%ZrO_(2) alloy has a smaller dislocation loop size than that of pure tungsten.It is proposed that the phase boundaries have the ability to absorb and annihilate defects and the addition of ZrO_(2) phase improves the sink strength for irradiation defects.It is confirmed that the W-1.5% ZrO_(2) alloy shows a smaller change in hardness than the pure tungsten after being irradiated.From the above results,we conclude that the addition of ZrO_(2) into tungsten can significantly reduce the accumulation of irradiated defects and improve the irradiation resistance behaviors of the tungsten materials.

关 键 词：W-ZrO_(2)alloy carbon ion irradiation MICROSTRUCTURE surface hardness 

分 类 号：TL34[核科学技术—核技术及应用] TG146.411[一般工业技术—材料科学与工程]