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

Shuhei Nogami, Dmitry Terentyev, Aleksandr Zinovev, Chao Yin, Michael Rieth, Gerald Pintsuk, Akira Hasegawa

Research output: Contribution to journalArticlepeer-review

1 Citation (Scopus)

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 effects. 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 temperature (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.

Original languageEnglish
Article number153009
JournalJournal of Nuclear Materials
Volume553
DOIs
Publication statusPublished - 2021 Sep

Keywords

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

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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