Methods and alloy systems for non-Be BMG matrix composite materials that can be used to additively manufacturing parts with superior mechanical properties, especially high toughness and strength, are provided. Alloys are directed to BMGMC materials comprising a high strength BMG matrix reinforced with properly scaled, soft, crystalline metal dendrite inclusions dispersed throughout the matrix in a sufficient concentration to resist fracture.

According to the present invention, provided is a zirconium-based metal glass alloy including, in atomic %, 62% or more and 67% or less of zirconium (Zr), 1% or more and 5% or less of niobium (Nb), 0.5% or more and 2% or less of titanium (Ti), 12% or more and 15% or less of copper (Cu), 8% or more and 10% or less of nickel (Ni), and 7.5% or more and 8.5% or less of aluminum (Al), the zirconium-based metal glass alloy having a composition represented by Zr.sub.62-67Nb.sub.1-5Ti.sub.0.5-2Cu.sub.12-15Ni.sub.8-10Al.sub.7.5-8.5.

According to the present invention, provided is a zirconium-based metal glass alloy including, in atomic %, 62% or more and 67% or less of zirconium (Zr), 1% or more and 5% or less of niobium (Nb), 0.5% or more and 2% or less of titanium (Ti), 12% or more and 15% or less of copper (Cu), 8% or more and 10% or less of nickel (Ni), and 7.5% or more and 8.5% or less of aluminum (Al), the zirconium-based metal glass alloy having a composition represented by Zr.sub.62-67Nb.sub.1-5Ti.sub.0.5-2Cu.sub.12-15Ni.sub.8-10Al.sub.7.5-8.5.

A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050° C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650° C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520° C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.

A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050° C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650° C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520° C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.

A vacuum insulated glass (VIG) window unit includes an array of spacers provided between at least a pair of substrates, such as glass substrate. Certain example embodiments relate to a VIG window unit including spacers (e.g., pillars) of or including a metal alloy. The metal alloy of the spacer may be an amorphous metal alloy (e.g., Zr and/or Cu based amorphous alloy). Such metal alloy spacers advantageously reduce the thermal conductivity of the spacer array and can increase the center of glass R-value of the VIG window unit.

A vacuum insulated glass (VIG) window unit includes an array of spacers provided between at least a pair of substrates, such as glass substrate. Certain example embodiments relate to a VIG window unit including spacers (e.g., pillars) of or including a metal alloy. The metal alloy of the spacer may be an amorphous metal alloy (e.g., Zr and/or Cu based amorphous alloy). Such metal alloy spacers advantageously reduce the thermal conductivity of the spacer array and can increase the center of glass R-value of the VIG window unit.

A process is described that includes forming a metal alloy component having a pre-specified three dimensional geometry for use in a nuclear reactor by an additive manufacturing process followed by annealing the formed component at a first annealing temperature within the alpha temperature range of the phase diagram for the metal alloy. A second annealing step at a second annealing temperature lower than the first annealing temperature may be added. Alternatively, annealing may be at an annealing temperature in the alpha+beta temperature range of a phase diagram for the metal alloy, followed by a second anneal in the alpha temperature range of the phase diagram for the metal alloy.

A treatment method for zirconium alloy includes performing a surface layer oxidation and removal treatment on a surface layer of zirconium alloy. The surface layer oxidation and removal treatment comprises performing an oxidation treatment on the surface layer of the zirconium alloy to obtain an oxide surface layer, and then removing the oxide surface layer to expose a metal substrate. A method for fabricating a surface oxide ceramic layer of zirconium alloy and a material for a medical implant are also provided.

The invention discloses a preparation method and application of an oxidized ceramic layer on the surface of zirconium and zirconium alloy. The method comprises the following steps: reducing the roughness of a target area to 0.01 μm or less, performing oxidation treatment in an oxidizing gas atmosphere, and replacing the oxidizing gas with inactive gas. According to the technical solution provided in the present application, the surface roughness is controlled before oxidation treatment, so that the surface roughness after oxidation treatment can satisfy the use requirements; and the inert gas replacement after surface oxidation treatment avoids the removal of a film layer with poor performance formed during the cooling process, thereby completely avoiding the need for later polishing treatment, maintaining the integrity and uniformity of the oxidized ceramic layer, and guaranteeing the protective performance.