4.7 Article

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

期刊

JOURNAL OF NUCLEAR MATERIALS
卷 542, 期 -, 页码 -

出版社

ELSEVIER
DOI: 10.1016/j.jnucmat.2020.152505

关键词

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

资金

  1. U.S. Department of Energy, Office of Fusion Energy Sciences [DE-AC05-00OR22725]
  2. UT-Battelle, LLC
  3. JSPS KAKENHI [17H01364]
  4. Grants-in-Aid for Scientific Research [17H01364] Funding Source: KAKEN

向作者/读者索取更多资源

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 degrees 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 degrees 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 degrees C, the ductility of K-doped W-3%Re after irradiation was significantly higher than that of Pure W. The irradiation at similar to 1000 degrees 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 similar to 1000 degrees C, and ductility was exhibited without an increase in strength. (C) 2020 Elsevier B.V. All rights reserved.

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