Highly uniform oxide dispersion-strengthened materials W–1 wt % Nd₂O₃ and W–1 wt % CeO₂ were successfully fabricated via a novel wet chemical method followed by hydrogen reduction. The powders were consolidated by spark plasma sintering at 1700 °C to suppress grain growth. The samples were characterized by performing field emission scanning electron microscopy and transmission electron microscopy analyses, Vickers microhardness measurements, thermal conductivity, and tensile testing. The oxide particles were dispersed at the tungsten grain boundaries and within the grains. The thermal conductivity of the samples at room temperature exceeded 140 W/m·K. The tensile tests indicated that W–1 wt % CeO₂ exhibited a ductile–brittle transition temperature between 500 °C and 550 °C, which was a lower range than that for W–1 wt % Nd₂O₃. Surface topography and Vickers microhardness analyses were conducted before and after irradiations with 50 eV He ions at a fluence of 1 × 10²² m⁻² for 1 h in the large-powder material irradiation experiment system. The grain boundaries of the irradiated area became more evident than that of the unirradiated area for both samples. Irradiation hardening was recognized for the W–1 wt % Nd₂O₃ and W–1 wt % CeO₂ samples.

Combining the advantages of a wet chemical method and spark plasma sintering, carbide-doped materials W-1wt%TiC and W-1wt%ZrC were prepared. Microstructural evolution in W-1wt%TiC and W-1wt%ZrC under irradiation of 5 keV He⁺ at 600 °C to fluences up to 5.0 × 10²¹ ions/m² with ion flux of about 8.8 × 10¹⁷ ions/m²s was investigated by transmission electron microscopy (TEM). The dislocation loop number density of W-1wt%TiC was higher than that of W-1wt%ZrC, but the average loop size of the W-1wt%TiC was in average smaller. There were no observable helium bubbles in W-1wt%TiC and W-1wt%ZrC, exhibiting higher radiation resistance to He⁺ compared to pure W. He⁺ pre-damaged and undamaged W-1wt%TiC and W-1wt%ZrC samples were irradiated by 5 keV D₂⁺ to estimate the D retention in doped W materials. The irradiation damage impact of He⁺ on deuterium retention was examined by a method of thermal desorption spectroscopy (TDS). Compared with the undamaged samples, it was illustrated that D₂ retention of W-1wt%TiC and W-1wt%ZrC increased after He⁺ pre-irradiation.

The extremely harsh environment of the high temperature plasma imposes strict requirements on the construction materials of the first wall in a fusion reactor. In this work, a refractory alloy system, WTaVTiZr_x, with low activation and high entropy, was theoretically designed based on semi-empirical formula and produced using a laser cladding method. The effects of Zr proportions on the metallographic microstructure, phase composition, and alloy chemistry of a high-entropy alloy cladding layer were investigated using a metallographic microscope, XRD (X-ray diffraction), SEM (scanning electron microscope), and EDS (energy dispersive spectrometer), respectively. The high-entropy alloys have a single-phase BCC structure, and the cladding layers exhibit a typical dendritic microstructure feature. The evolution of microstructure and mechanical properties of the high-entropy alloys, with respect to annealing temperature, was studied to reveal the performance stability of the alloy at a high temperature. The microstructure of the annealed samples at 900 °C for 5–10 h did not show significant changes compared to the as-cast samples, and the microhardness increased to 988.52 HV, which was higher than that of the as-cast samples (725.08 HV). When annealed at 1100 °C for 5 h, the microstructure remained unchanged, and the microhardness increased. However, after annealing for 10 h, black substances appeared in the microstructure, and the microhardness decreased, but it was still higher than the matrix. When annealed at 1200 °C for 5–10 h, the microhardness did not increase significantly compared to the as-cast samples, and after annealing for 10 h, the microhardness was even lower than that of the as-cast samples. The phase of the high entropy alloy did not change significantly after high-temperature annealing, indicating good phase stability at high temperatures. After annealing for 10 h, the microhardness was lower than that of the as-cast samples. The phase of the high entropy alloy remained unchanged after high-temperature annealing, demonstrating good phase stability at high temperatures.

The insufficient bond strength between a rigid ceramic bracket and an enamel leads to bracket detachment and orthodontic treatment failure. In this work, a laser-based engineering route with high controllability, high efficiency, and low cost is applied to texture ceramic brackets with surface microstructures to introduce mechanical retention for improved bonding between ceramic brackets and enamels. The influence of the structural features of surface microstructure on the shear bond strength (SBS) of laser-textured ceramic brackets with enamels is systematically studied. The maximum SBS value of 575 ± 25.16 N is obtained for a ceramic bracket that is textured with a surface grid pattern that has a grid size of 80 μm and a groove depth of 37 μm. This SBS value is about four times higher than an untreated bracket. A bracket-resin-enamel model is established to theoretically understand the stress distribution and mechanical behavior of the system under a shear load. The theoretical simulation results evidence concentrated stress at the groove area, suggesting the formation of mechanical retention. The development of a laser surface texturing method to improve the bonding strength of ceramic brackets could promote the bonding reliability of ceramic brackets in orthodontic treatment.