中国物理B ›› 2022, Vol. 31 ›› Issue (9): 96102-096102.doi: 10.1088/1674-1056/ac6b25
Microstructure and hardening effect of pure tungsten and ZrO2 strengthened tungsten under carbon ion irradiation at 700℃
Chun-Yang Luo(罗春阳)1,2,†, Bo Cui(崔博)1,†, Liu-Jie Xu(徐流杰)2,‡, Le Zong(宗乐)2, Chuan Xu(徐川)3, En-Gang Fu(付恩刚)3, Xiao-Song Zhou(周晓松)1, Xing-Gui Long(龙兴贵)1, Shu-Ming Peng(彭述明)1, Shi-Zhong Wei(魏世忠)2, and Hua-Hai Shen(申华海)1,2,§
- 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
Microstructure and hardening effect of pure tungsten and ZrO2 strengthened tungsten under carbon ion irradiation at 700℃
Chun-Yang Luo(罗春阳)1,2,†, Bo Cui(崔博)1,†, Liu-Jie Xu(徐流杰)2,‡, Le Zong(宗乐)2, Chuan Xu(徐川)3, En-Gang Fu(付恩刚)3, Xiao-Song Zhou(周晓松)1, Xing-Gui Long(龙兴贵)1, Shu-Ming Peng(彭述明)1, Shi-Zhong Wei(魏世忠)2, and Hua-Hai Shen(申华海)1,2,§
- 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
摘要： Microstructure evolution and hardening effect of pure tungsten and W-1.5%ZrO2 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%ZrO2 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 ZrO2 phase improves the sink strength for irradiation defects. It is confirmed that the W-1.5%ZrO2 alloy shows a smaller change in hardness than the pure tungsten after being irradiated. From the above results, we conclude that the addition of ZrO2 into tungsten can significantly reduce the accumulation of irradiated defects and improve the irradiation resistance behaviors of the tungsten materials.
中图分类号: (Metals and alloys)
- 61.82.Bg