Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten

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Authors

Institutes & Expert groups

  • Tohoku University
  • IKET KIT INE - Karlsruhe Institute of : Institute for Nuclear Waste Disposal
  • FZJ - Forschungszentrum Jülich GmbH

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Abstract

Tungsten (W) based materials for fusion reactor applications have been developed in Japan for the last decade to improve thermo-mechanical properties and tolerance with respect to neutron-irradiation ef- fects. Potassium (K) doping for dispersion strengthening and alloying by rhenium (Re) for solid solute softening and strengthening were applied to W fabricated by powder metallurgy. Thereby modified W materials, e.g. K-doped W and K-doped W-3%Re, demonstrated a higher recrystallization temperature threshold, an increase in strength and ductility, and a reduction in ductile-to-brittle transition temper- ature (DBTT) compared to pure W in the non-irradiated state. Embrittlement caused by displacement damage and its amplification due to solid transmutation products is expected to be an intrinsic issue of W based materials under neutron irradiation environment inherent to future fusion reactors. In this paper, the effect of K-doping and alloying by Re on the neutron-irradiation-induced embrittlement of W was investigated at neutron fluence causing a considerable amount of solid transmutation products.

Details

Original languageEnglish
Article number153009
Pages (from-to)1-11
Number of pages11
JournalJournal of Nuclear Materials
Volume553
DOIs
Publication statusPublished - 29 Apr 2021

Keywords

  • Tungsten, Potassium doping, Alloying by rhenium, Neutron irradiation, Embrittlement

ID: 7277042