TEM studies of 1 MeV Fe+ ion-irradiated W alloys by wet chemical method: High-temperature annealing and deuterium retention

  • Xiao Yu Ding
  • , Jia Qin Liu
  • , Lai Ma Luo
  • , Qiu Xu
  • , Xiang Gao
  • , Jian Jun Huang
  • , Bin Yu
  • , Jian Gang Li
  • , Yu Cheng Wu

Research output: Contribution to journalArticlepeer-review

6 Scopus citations

Abstract

In this study, the microstructural changes in irradiated W-1 wt%Pr2O3, W-1 wt%La2O3, W-1 wt%TiC and W-1 wt%ZrC specimens by 1 MeV Fe+ ion irradiation to doses of 1 dpa at room temperature have been characterized by transmission electron microscopy (TEM) to understand the radiation damage. The specimens of 1 dpa were consecutively annealed at temperatures of 600 °C, 800 °C, 900 °C and 1100 °C for 1 h, and the post-irradiation annealing effect on the microstructure was studied. Microstructural features such as dislocations, dislocation loops and dense dislocation networks were observed by the means of TEM. There was a significant change in the microstructure of the tungsten (W) after irradiation and post-irradiation annealing. W-1 wt%TiC likely consisted of fewer radiation-induced defects and hence exhibits higher resistance to radiation-induced microstructural changes than the others. The general trend is that the density of defect clusters decreases while the average size of the clusters increases with the annealing temperature. A complete removal of dislocation structures at 1100 °C occurred in all materials. The irradiation damage effect of Fe+ ions on the deuterium retention of as-synthesized W-based composites was investigated. Thermal desorption spectroscopy of W implanted with ions was performed using the low-energy ion irradiation system of Kyoto University. Compared with the samples without Fe+ pre-irradiation, the deuterium retention of the four composites increased after Fe+ pre-irradiation. The retained amount of deuterium was also increased with the increase in the Fe+ irradiation dose. This is of vital importance to the scientific community working on these materials for extreme irradiating environments.

Original languageEnglish
Article number016008
JournalNuclear Fusion
Volume59
Issue number1
DOIs
StatePublished - 2019

Keywords

  • annealing effect
  • deuterium retention
  • ion irradiation
  • microstructure evolution
  • TEM
  • tungsten

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