TY - JOUR
T1 - Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures
AU - Miyazawa, Takeshi
AU - Garrison, Lauren M.
AU - Geringer, Josina W.
AU - Echols, John R.
AU - Fukuda, Makoto
AU - Katoh, Yutai
AU - Hinoki, Tatsuya
AU - Hasegawa, Akira
N1 - Funding Information:
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 .
Publisher Copyright:
© 2020 Elsevier B.V.
PY - 2020/12/15
Y1 - 2020/12/15
N2 - 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.
AB - 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.
KW - Neutron irradiation
KW - Polycrystalline tungsten
KW - Recrystallization
KW - Tensile properties
KW - Thermal neutron shield
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U2 - 10.1016/j.jnucmat.2020.152505
DO - 10.1016/j.jnucmat.2020.152505
M3 - Article
AN - SCOPUS:85091657972
VL - 542
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
M1 - 152505
ER -