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To investigate the surface damage of a material by He ions, a dispersion-strengthened W-1wt%TiC alloy was irradiated by 5-keV He ions at 773 K, 973 K, and 1173 K up to an ion dose of 1.8 × 1021 He m−2, respectively. No He bubble formation was observed under transmission electron microscopy at any temperature for He doses less than 1.5 × 1020 He m−2. When this dose was exceeded, He bubbles grew and...
Considering that tungsten (W) materials served as the plasma-facing material in the fusion reactor would be exposed to edge-localized modes (ELMs)-like thermal shock loading accompanied with He-ion irradiation, the W–TiC composite produced with a wet-chemical method was conducted by the dual effects from the laser beam thermal shock first and He-ion irradiation later in this work. The microstructure...
Crystalline WO3/Ti-doped WO3 bi-layer nanopore arrays were constructed by the template synthesis of a WO3 nanopore layer modified by a magnetron sputtering of an amorphous Ti-doped/WO3 layer. The obtained bi-layer nanopore array shows a remarkable electrochromic performance with large dual-band optical modulation in both visible (VIS) and near infrared (NIR) regions (optical modulation of over 70%...
Y2O3-doped tungsten (W–Y2O3) composite powders prepared by a traditional chemical co-precipitation method possess obvious bimodal distribution in size, which would deteriorate their sintering properties. The bimodal distribution can be effectively eliminated by an improved chemical co-precipitation method, in which the cationic surfactant cetyltrimethylammonium bromide (CTAB) was innovatively employed...
Hardmetals are tungsten carbide (WC)-based composites, which are made of WC as a hard phase and transition metals such as Co, Fe, or/and Ni as ductile binder matrices. Their properties can be mainly tailored through the grain sizes of the sintered carbides and the amount of metallic binder. As successful tool materials, hardmetals are widely applied in metal cutting, wear applications, chipless forming,...
One key challenge for the development of fusion energy is plasma-facing materials. Tungsten-based materials are promising candidates for plasma-facing components (PFCs) in the magnetic confinement nuclear fusion reactors because of their high melt temperature, high-thermal conductivity, high-thermal load resistance, low tritium retention, and low sputtering yield. In fusion reactors, PFCs are exposed...
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