Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures

Takeshi Miyazawa, Lauren M. Garrison, Josina W. Geringer, John R. Echols, Makoto Fukuda, Yutai Katoh, Tatsuya Hinoki, Akira Hasegawa

Research output: Contribution to journalArticlepeer-review

4 Citations (Scopus)

Abstract

The tensile properties of powder-metallurgical-processed Pure W, K-doped W, W-3%Re, and K-doped W-3%Re were examined after neutron irradiation up to 0.7 dpa at 910–1020 °C with a thermal neutron shield in the High Flux Isotope Reactor (HFIR). After irradiation, recrystallized Pure W (R) exhibited a brittle fracture mode, while recrystallized K-doped W-3%Re (R) exhibited a ductile fracture mode at 500 °C. K-doped W-3%Re (R) has fine grains, and hence, contains a considerable number of grain boundaries that act as sinks for irradiation defects. Solid solute Re in the W matrix could improve not only the mechanical properties of W, but also its resistance to neutron irradiation. At 500 °C, the ductility of K-doped W-3%Re after irradiation was significantly higher than that of Pure W. The irradiation at ~1000 °C did not induce hardening of stress-relieved (SR) W materials, but SR W materials tended to exhibit a decrease in the ultimate tensile strength (UTS) and an increase in total elongation (TE). The softening due to the recovery and recrystallization of SR W materials and the hardening due to the formation of irradiation defect clusters were balanced during irradiation at ~1000 °C, and ductility was exhibited without an increase in strength.

Original languageEnglish
Article number152505
JournalJournal of Nuclear Materials
Volume542
DOIs
Publication statusPublished - 2020 Dec 15
Externally publishedYes

Keywords

  • Neutron irradiation
  • Polycrystalline tungsten
  • Recrystallization
  • Tensile properties
  • Thermal neutron shield

ASJC Scopus subject areas

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

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