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

26 Scopus citations

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
StatePublished - Dec 15 2020

Funding

The authors thank the ORNL LAMDA Technical Team for technical assistance. This study was performed as a part of the US?Japan PHENIX Collaboration Project on Technological Assessment of Plasma Facing Components for DEMO Reactors. The ORNL research was sponsored by the U.S. Department of Energy, Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. This study was supported by JSPS KAKENHI, Grant Number 17H01364. The authors thank the ORNL LAMDA Technical Team for technical assistance. This study was performed as a part of the US–Japan PHENIX Collaboration Project on Technological Assessment of Plasma Facing Components for DEMO Reactors. The ORNL research was sponsored by the U.S. Department of Energy , Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. This study was supported by JSPS KAKENHI, Grant Number 17H01364 .

Keywords

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

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