Microstructural development of neutron irradiated W-Re alloys

Yoshiyuki Nemoto, Akira Hasegawa, Manabu Satou, Katsunori Abe

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104 Citations (Scopus)


Tungsten (W) alloys are candidate materials to be used as high-heat-flux materials in fusion reactors. In our previous work, W-26 wt% Re showed drastic hardening and embrittlement after the neutron irradiation. In this study, to clarify the irradiation hardening and embrittlement behavior of W-26 wt% Re, from the viewpoint of microstructural development, the microstructure observation of the neutron irradiated W-26 wt% Re was carried out using transmission electron microscope (TEM). The specimens were irradiated at the materials open test assembly of the fast flux test facility (FFTF/MOTA-2A cycle 11) up to ∼1 × 1027 n/m2, (En > 0.1 MeV). The irradiation temperatures were 646, 679, 792, 873 and 1073 K. In all neutron irradiated W-26 wt% Re samples, sigma-phase precipitates and chi-phase precipitates were observed, while in the thermally aged specimen, only sigma-phase precipitates were observed. Irradiation effects on microstructural development are discussed.

Original languageEnglish
Pages (from-to)1144-1147
Number of pages4
JournalJournal of Nuclear Materials
Issue numberPART II
Publication statusPublished - 2000

ASJC Scopus subject areas

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


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