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The effect of annealing treatment on plasma induced surface blistering and deuterium retention in tungsten

  • Zhenyu Jiang
  • , Wenjie Zhang
  • , Honghui Zhang
  • , Tianyi Song
  • , Yong Liu
  • , Xiaochun Li
  • , Kaigui Zhu*
  • *此作品的通讯作者
  • Beihang University
  • CAS - Institute of Plasma Physics

科研成果: 期刊稿件文章同行评审

摘要

Hydrogen isotope retention and surface blistering in tungsten, which is regarded as a primary candidate for plasma-facing materials in fusion reactors, can degrade its performance. Annealing treatment is commonly used to relieve residual stress but can also alter the defect density and influence the blistering and deuterium retention behaviors. In this work, the blistering and deuterium retention behaviors of samples unannealed and annealed at 1273 K were investigated. To further clarify the effects of annealing temperature, samples were annealed at 473 K, 673 K, 873 K, 1073 K and 1273 K, respectively, with an unannealed sample and a sample recrystallized at 1973 K serving as references. Nanoindentation tests revealed that the bulk equivalent hardness remains relatively stable until it begins to decrease when the annealing temperature exceeds 1073 K. The maximum shear stress, calculated based on pop-in events, increases with annealing temperature, indicating a decreasing trend in dislocation density. Then the samples were exposed to deuterium plasma with a flux of 5.2 × 1018 D/(m2∙s) and a fluence of 2.0 × 1023 D/m2. Blisters were observed on the surface of samples except the recrystallized one. The average sizes of blisters on each sample are similar, while the densities of blisters exhibit an abrupt drop when annealed at 1073 K. The deuterium retention of samples was analyzed by thermal desorption spectroscopy (TDS) and it decreases as annealing temperature increases. The desorption curves were fitted by TMAP7 code and the fitted results suggest a decreasing concentration of traps. All the results indicate that annealing reduces defect density, thereby mitigating blistering and decreasing deuterium retention.

源语言英语
文章编号156758
期刊Journal of Nuclear Materials
630
DOI
出版状态已出版 - 8月 2026

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