Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

Hanns Gietl, Takaaki Koyanagi, Xunxiang Hu, Makoto Fukuda, Akira Hasegawa, Yutai Katoh

研究成果: Article査読

11 被引用数 (Scopus)

抄録

To understand the microstructural stability of candidate plasma-facing materials under fusion-relevant environments, neutron irradiation of W and W-3%Re alloys with and without K and La dopants was performed in the mixed-spectrum High Flux Isotope Reactor at nominal temperatures of ~850 °C and ~1100 °C to calculated doses between 0.42 and 0.47 dpa. To the best of our knowledge, this study presents the first experimental evidence of radiation-enhanced recrystallization in W and undoped W–Re alloys at ~850 °C, conditions where thermal annealing does not cause any grain growth in a similar timescale. Potassium- or lanthanum-doped tungsten alloys showed more resistance to radiation-enhanced grain growth. We explain the acceleration of grain growth by analyzing the self-diffusion constant under atomic displacement environments. The microstructural observations of the studied W variants suggest that La doping is more effective than K doping for mitigating recrystallization. This study also found that radiation-enhanced recrystallization is an important consideration when designing and applying W to plasma-facing components in future nuclear fusion reactors.

本文言語English
論文番号163419
ジャーナルJournal of Alloys and Compounds
901
DOI
出版ステータスPublished - 2022 4月 25
外部発表はい

ASJC Scopus subject areas

  • 材料力学
  • 機械工学
  • 金属および合金
  • 材料化学

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