Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

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

doi:10.1016/j.jallcom.2021.163419

Title: Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

Journal Article · 23 December 2021 · Journal of Alloys and Compounds

DOI: https://doi.org/10.1016/j.jallcom.2021.163419 · OSTI ID:1840183

Gietl, Hanns ^[1]; Koyanagi, Takaaki ^[1]; Hu, Xunxiang ^[2]; Fukuda, Makoto ^[3]; Hasegawa, Akira ^[4]; Katoh, Yutai ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sichuan Univ., Chengdu (China)
National Institutes for Quantum and Radiological Science and Technology, Naka, Ibaraki (Japan)
Tohoku Univ., Sendai (Japan)

Herein, 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.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: Science Specialty Program of Sichuan University; USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1840183

Journal Information:: Journal of Alloys and Compounds, Journal Name: Journal of Alloys and Compounds Journal Issue: 901 Vol. 901; ISSN 0925-8388

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
Neutron irradiation
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Title: Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys

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