1129 results about "Zirconium alloy" patented technology

The invention presented herein relates to a niobium-containing zirconium alloy for use in nuclear fuel cladding. The Zr alloy of this invention with superior corrosion resistance is characterized as comprising an alloy composition as follows:1) niobium (Nb), in a range of 0.8 to 1.2 wt. %; one or more elements selected from the group consisting of iron (Fe), molybdenum (Mo), copper (Cu) and manganese (Mn), in a range of 0.1 to 0.3 wt. %, respectively; oxygen (O), in a range of 600 to 1400 ppm; silicon (Si), in a range of 80 to 120 ppm; and the balance being of Zr,2) Nb, in a range of 1.3 to 1.8 wt. %; tin (Sn), in a range of 0.2 to 0.5 wt. %; one element selected from the group consisting of Fe, Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr,3) Nb, in a range of 1.3 to 1.8 wt. %; Sn, in a range of 0.2 to 0.5 wt. %; Fe, in a range of 0.1 to 0.3 wt. %; one element selected from the group consisting of chromium (Cr), Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr, and4) Nb, in a range of 0.3 to 1.2 wt. %; Sn, in a range of 0.4 to 1.2 wt. %; Fe, in a range of 0.1 to 0.5 wt. %; one element selected from the group consisting of Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr.

A method is described herein for coating the substrate of a component for use in a water cooled nuclear reactor to provide a barrier against corrosion. The method includes providing a zirconium alloy substrate; and coating the substrate with particles selected from the group consisting of metal oxides, metal nitrides, FeCrAl, FeCrAlY, and high entropy alloys. Depending on the metal alloy chosen for the coating material, a cold spray or a plasma arc spray process may be employed for depositing various particles onto the substrate. An interlayer of a different material, such as a Mo, Nb, Ta, or W transition metal or a high entropy alloy, may be positioned in between the Zr-alloy substrate and corrosion barrier layer.

A coating of blue-black or black oxidized zirconium of uniform and controlled thickness on a zirconium or zirconium alloy material is accomplished through the oxidative treatment of an amorphous zirconium or zirconium alloy substrate having an altered surface roughness. An oxidized zirconium coating of uniform and controlled thickness is especially useful on orthopedic implants of zirconium or zirconium-based alloys to provide low friction, highly wear resistant surfaces on artificial joints, such as, but not limited to, hip joints, knee joints, shoulders, elbows, and spinal implants. The uniformly thick oxidized zirconium surface of controlled depth on prostheses provide a barrier against implant corrosion caused by ionization of the metal prostheses. The invention is also useful in non-articulating implant devices such as bone plates, bone screws, etc.

The invention provides a process for the production of a composite structural part which can withstand high thermal stress, consisting of at least one graphite part and at least one metal part made of a hardenable copper alloy. In accordance with the invention, the metal part is bonded, by a hot isostatic press process, with the graphite part, which has a layer made of copper or a copper alloy on the bonding surface. In this way, it is possible to use copper-chromium-zirconium alloys with more complex composite structural part constructions and with thin-wall parts of the metal component, without the good mechanical characteristics of the copper-chromium-zirconium alloy being destroyed.

An amorphous Zr alloy has a composition expressed as Zr-Ala-Nib-Cuc-Md. M is one or more elements selected from Ti, Nb and Pd. The a, b, c, and d are amounts in atomic %, and satisfy the following formulas. 5<=a<=0; 30<=b+c<=50; b/c<=1/3; and 0<d<=7. The remainder are Zr and inevitable impurities. The alloy contains a non-crystalline phase of 90% or higher by volume. Also, the amorphous alloy indicates an excellent glass-forming ability with a supercooled liquid range over 100° C. (indicated by a difference between the crystallization temperature and the glass transition temperature) and which has a thickness of 1 mm or thicker. Further, it has excellent strength and toughness indicated by the following mechanical characteristics: tensile strength of 1800 MPa or higher; flexural strength of 2500 MPa or higher; Charpy impact value of 100 kJ/m2 or higher; and fracture toughness value of 50 MPa*m1/2 or higher.

The invention discloses a high-strength high-conductivity copper-chromium-zirconium alloy and a preparation method of a plate/strip thereof. This alloy comprises the chemical composition: 0.01-1.5 wt% of Cr, 0.01-0.5 wt% of Zr, 0.001-0.5 wt% of Ti, 0.01-0.5 wt% of Mn, 0.0001-0.07 wt% of Ca, and the balance of copper and unavoidable impurities; the position and process of the Cu-Cr-Zr alloy are optimized, the provided high-strength high-conductivity copper-chromium-zirconium alloy retains high conductivity (above 80% IACS), elastic modulus up to higher than 130 GPa, softening temperature resistance up to higher than 500 DEG C, yield strength up to higher than 550 MPa and hardness up to 160 HV, the copper-chromium-zirconium plate/strip is imparted high strength, high conductivity and excellent comprehensive performance, this comprehensive performance meets the requirements of products such as a lead frame and a connector upon base material stamping and machining performances, and this plate/strip material is mainly applied to electronic components such as connectors and lead frames.

The invention discloses a copper-chromium-zirconium alloy contact wire and a production technique thereof. The copper-chromium-zirconium alloy contact wire is composed of copper, chromium, zirconium and inevitable impurity elements according to the set mass percentages. In preparation, the main technique comprises the steps of raw material preparation, up-drawing continuous casting, CONFORM continuous squeezing, primary cold machining, solution treatment, secondary cold machining, aging treatment and finished product drawing. According to the copper-chromium-zirconium alloy contact wire manufactured by the technique and materials, the matching of the contact wire raw materials is reasonably adjusted, the ratio of all element components in the contact wire is adjusted, and the special production technique is combined so that a high-strength high-conductivity contact wire product can be produced, wherein the weight of one single contact wire product is larger than two tons, the IACS electrical conductivity of the contact wire product is 75-90%, and the tensile strength of the contact wire product is 550-700 MPa; and the requirement of current electric railway high-speed development can be better met.

The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.

The invention relates to a magnesium-calcium-carbon refractor material, in particular to a refractory material for smelting, which belongs to the technical field of refractory materials for smelting. The magnesium-calcium-carbon refractor material contains 1-25 parts of carbon, 0.2-6 parts of a magnesium-zirconium alloy, 60-96 parts of a mixture of dolomite sand, magnesium-calcium sand and magnesium sand, and 2-5 parts of a carbon-containing bonding agent, wherein the magnesium-zirconium alloy contains 3-35 percent of a zirconium element and the balance of magnesium and a small quantity of impurities. The magnesium-calcium-carbon refractor material provided by the invention can be taken as a refractory material for smelting, and has the advantages of oxidation resistance, high temperature resistance, slag permeation resistance, thermal shock resistance and easiness in producing.

Articles, such as tubing or strips, which have excellent corrosion resistance to water or steam at elevated temperatures, are produced from alloys having 0.2 to 1.5 weight percent niobium, 0.01 to 0.45 weight percent iron, at least one additional alloy element selected from 0.02 to 0.8 weight percent tin, 0.05 to 0.5 weight percent chromium, 0.02 to 0.3 weight percent copper, 0.1 to 0.3 weight percent vanadium, 0.01 to 0.1 weight percent nickel, the balance at least 97 weight percent zirconium, including impurities, wherein the alloy may be fabricated from a process of forging the zirconium alloy into a material, beta quenching the material, forming the material by extruding or hot rolling the material, cold working the material with one or a multiplicity of cold working steps, wherein the cold working step includes cold reducing the material and annealing the material at an intermediate anneal temperature of 960°-1105° F., and final working and annealing of the material. The articles formed also show improved weld corrosion resistance with the addition of chromium.

The invention relates to a method for processing a thin-walled tube of zirconium alloy specially used by nuclear reactor with the specification of Phi 12.8 multiplied by 0.25mm. The adopted technical scheme is characterized by comprising the following steps: selecting and using a zircaloy tube (1) with a certain length of Phi 44.5 multiplied by 7.65 mm, then conducting the steps such as cold rolling, primary intermediate annealing, primary acid cleaning, second pass cold rolling, secondary intermediate annealing, secondary acid cleaning, final cold rolling, final annealing, straightening and then polishing, acid cleaning and complexing treatment, detection and then cutting constant length, and the like on the zircaloy tube, and finally completing the process of the thin walled tube of zirconium alloy specially used by the nuclear reactor. The thin-walled tube of zirconium alloy specially used by the nuclear reactor which is processed by the method reaches the requirement of the required machining accuracy, meets the operating requirement of the nuclear reactor, and changes the unfavorable situation that in China, the thin-walled tube of zirconium alloy specially used by the nuclear reactor, which has the specification and the machining accuracy, depends on import.

The invention discloses a zirconium and zirconium alloy zinc-manganese composite phosphating solution and a phosphating method thereof. The zirconium and zirconium alloy zinc-manganese composite phosphating solution is an aqueous solution comprising the following components of: 0.001-10g of zinc salts, 0.001-5g of manganese salts, 5-30g of phosphoric acid, 1-8g of accelerator, 0.001-15g of complexing agent, 0.001-10g of anionic surface agent and 0.001-5g of corrosion inhibitor in each liter of phosphating treatment solution. The phosphating method of the zirconium and zirconium alloy zinc-manganese composite phosphating solution comprises the steps of preliminary grinding, water washing, chemical degreasing, water washing, acid pickling, water washing, phosphating, water washing and drying, wherein the phosphating treatment temperature is 50-90DEG C, the pH value is 1.5-3.5 and the treatment time is 1-30 minutes. According to the zirconium and zirconium alloy zinc-manganese composite phosphating solution and the phosphating method thereof disclosed by the invention, a phosphate conversion coating with favorable protective performance, favorable wear resistance, fineness and uniformity can be obtained from the surfaces of zirconium and zirconium alloy workpieces. The phosphate conversion coating is stable and strong in a binding force and can be used for improving the service performances of zirconium and zirconium alloy and prolonging the service life of the zirconium and zirconium alloy. The phosphating method disclosed by the invention is stable in process, easy to control and is environment-friendly.

A coating of blue-black or black oxidized zirconium of uniform and controlled thickness on a zirconium or zirconium alloy material is accomplished through the use of a single phase crystalline material substrate having an altered surface roughness. An oxidized zirconium coating of uniform and controlled thickness is especially useful on orthopedic implants of zirconium or zirconium-based alloys to provide low friction, highly wear resistant surfaces on artificial joints, such as, but not limited to, hip joints, knee joints, shoulders, elbows, and spinal implants. The uniformly thick oxidized zirconium surface of controlled depth on prostheses provide a barrier against implant corrosion caused by ionization of the metal prostheses. The invention is also useful in non-articulating implant devices such as bone plates, bone screws, etc.

The invention relates to a FeCrAl alloy material for preparing a Nuclear reactor fuel cladding material. By taking the total weight of the FeCrAl alloy material as a benchmark, the FeCrAl alloy material is composed of the following components: 5%-25% of Cr, 3%-15% of Al, 0.01%-3.3% of Si, 0.001%-1% of Y, 5% or less of Mo, 5% or less of Nb, 1000 ppm or less of C, 1000 ppm or less of N and the balance of Fe and inevitable trace elements. The nuclear fuel cladding FeCrAl alloy has excellent oxidation resistance at the 1200 DGE C water vapor environment, which is obviously better than commercial M5 zirconium alloys, and the requirement for accident fault tolerance of the nuclear power plant is met. The alloy can be used for the preparation of oxide dispersion strengthened iron-base alloy base materials for fuel element cladding pipes, composite cladding pipes, zirconium alloy coatings and nuclear fuel cladding pipes, and core structural materials of positioning grid stripes and the like.

The invention relates to the technical field of material processing, in particular to a preparation method of a high-conductivity high-strength copper chromium zirconium alloy thin line conductor. The preparation method comprises the following main steps: performing alloy smelting and blank forming, performing cold deformation processing on rod blanks and line blanks, performing multi-stage solution treatment, and performing aging treatment. According to the preparation method, the copper chromium zirconium alloy rod blanks obtained through a specific preparation formula and a smelting process are subjected to the multi-stage solution treatment and the aging treatment in multi-stage rolling and drawing cold-working processes, so that the sizes, shapes and distribution of precipitated phases in the copper chromium zirconium alloy processing process are effectively controlled, the mechanical performance of materials is improved, and good conductivity of copper-based alloy is kept.

Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at beta phase range; beta-quenching the forged ingot after solution heat-treatment at 1015-1075° C.; hot-working the quenched ingot at 600-650° C.; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600° C., wherein temperatures of intermediate vacuum annealing and final vacuum annealing after beta-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (SIGMA A) is limited to 1.0x10-18 hr or lower.

The invention discloses a zirconium cladding surface resistant to high temperature and oxidation ZrCrFe/AlCrFeTiZr composite gradient coating preparing technology. Ultrahigh vacuum multitarget co-sputtering technique is adopted, a ZrCrFe/AlCrFeTiZr composite gradient alloy resistant to high temperature and oxidation protecting coating is prepared on the surface of a zirconium alloy base body, and the zirconium cladding surface resistant to high temperature and oxidation ZrCrFe/AlCrFeTiZr composite gradient coating preparing technology comprises the steps of predepositional treatment, bias voltage anti-splash washing and ZrCrFe/AlCrFeTiZr composite gradient alloy coating deposition. The preparing process of the composite coating is divided into two steps, the first step is to prepare ZrCrFe gradient transition layer coating, in a deposited ZrCrFe transition layer, the atomic percentage content of Zr element is changed from the gradient of 100 at%-35 at% in the thickness direction, the atomic percentage content of Cr element is changed from the gradient of 0 at%-33 at% in the thickness direction, and the atomic percentage content of Fe element is changed from the gradient of 0 at%-33 at% in the thickness direction; the second step is to prepare a AlCrFeTiZr high-entropy alloy coating, in a deposited AlCrFeTiZr high-entropy alloy coating, the atomic percentage content of Al element is controlled in 0.5 at%-1.0at %, and the atomic percentage of other elements is between 10 at%-35 at%. Bonding force of the coating prepared by the technology is excellent, the surface is dense and uniform, and the coating has excellent performance such as high strength, resistance to high temperature and oxidation and irradiation resistance.

The invention discloses a laser cladding method for preparing a nickel-based heat-resisting and wear-resisting coating on the surface of a zirconium alloy. The laser cladding method comprises the steps of polishing and washing the surface of a zirconium alloy matrix to be subjected to laser cladding; fully mixing nickel-based alloy powder and an organic binder, blending into a uniform paste, and uniformly coating the paste on the surface of the zirconium alloy matrix to be subjected to laser cladding in advance; introducing argon in advance before performing laser cladding; performing single-channel radiation scanning cladding on a powder pre-placing area on the surface of the zirconium alloy matrix by using laser beams, wherein technological parameters are as follows: the laser power is 2.0-3.8kW, the beam spot diameter is 5mm, the scanning speed is 3-5mm/s, the shielding gas flow rate is 8-15L/min, the laser cladding process is continuously operated, and the dilution rate is not more than 10%. By adopting the laser cladding method disclosed by the invention, the nickel-based heat-resisting and wear-resisting coating is prepared in situ on the surface of the zirconium alloy by using a laser in-situ cladding technique; the laser cladding method is simple and easy in operation process, noise-free, environment-friendly and pollution-free, and can reduce the energy consumption and production cost; the wear-resisting coating is excellent in performance, and can meet operating requirements.

A hydrogen permeable membrane which has an excellent high-temperature amorphous stability and a long lifetime under high-temperature heating operation and which can be miniaturized for use in a high-performance hydrogen purifier. The hydrogen permeable membrane is made of a non-crystalline nickel-zirconium alloy or zirconium-nickel alloy composed of 44 to 75 atom % of nickel or zirconium; and 0.2 to 16 atom % of aluminum, 0.2 to 12 atom % of vanadium and/or niobium, or 0.2 to 12 atom % of niobium and 0.1 to 10 atom % of phosphorus (provided that the combined amount of niobium and phosphorus is not more than 18 atom %); with the balance being zirconium or nickel and unavoidable impurities.

The invention relates to a high-strength and high-conductivity copper-chromium-zirconium alloy material and a preparation method thereof. The material is composed of, by weight, 0.5-1.5% of Cr, 0.05-0.3% of Zr, 0.02-0.1% of Mg, 0.005-0.01% of Si, 0.002-0.005% of Fe and the balance Cu. The alloy further includes two of the four elements: Ti, La, B and Ca, the content of each element is 0.001-0.005%, and the total content of the alloy elements is 0.005-0.01%. The material is prepared through smelting and casting, hot rolling, face milling, rough rolling, intermediate annealing, intermediate rolling, high-temperature rapid solution treatment, finish rolling and aging treatment. The high-strength and high-conductivity copper-chromium-zirconium alloy material has the tensile strength of 500-800MPa, the yield strength of 350-700 MPa, the elongation of 3-10%, the electrical conductivity of 75-90% IACS and the softening temperature of 500-600 DEG C, the stress relaxation after treatment for 1000 hours at 150 DEG C is smaller than 10%, and the transverse or longitudinal section does not crack after bending by 90 or 180 degrees under the condition: R/t<=1.5. The use requirements of precision plug-in terminals of high-end electronic components for copper alloy materials are completely met.

The invention relates to a method for preparing a zirconium and zirconium alloy investment precision casting oxide ceramic molding shell. At present, the most common methods for casting of active organic metal and alloy comprise machining graphite mold casting and investment precision casting. The most serious technological difficulty of the zirconium alloy investment precision casting is to manufacture an investment precision casting molding shell which has the advantages of high-temperature resistance, high chemical stability, high strength and high surface finish. The process of the invention comprises the following steps of: (1) preparing a coating, immersing a wax mould into paste, coating the paste, and coating a back layer; (2) removing wax by drying; and (3) roasting the coating in an electric furnace. The molding shell has the advantages of superior high-temperature chemical stability and high-temperature strength and can bear the high temperature of over 2,000 DEG C. A zirconium and zirconium alloy casting produced by using the shell manufacturing process has high surface quality, surface roughness Ra of less than or equal to 3.2mu m and surface pollution layer thickness of less than 100mu m. The complex zirconium and zirconium alloy casting with wall thickness of less than 3mm can be produced.

Example embodiments are directed to providing a thin, adherent coating on the surfaces of nuclear reactor components, which are known to cause increased corrosion on adjacent zirconium alloy structures, and methods of reducing the increased corrosion. Example embodiments include coatings being structurally bonded to components such that the difference in the corrosion potential between a coated component and a zirconium alloy component is less than that between a component without the coating and the zirconium alloy component.

The invention provides electrolyte. The electrolyte is aqueous solution; and the aqueous solution contains fluorozirconate, borofluoride, water-soluble carboxylate of zinc and alkali metal hydroxide. The invention also provides a zirconium or zirconium alloy surface micro-arc oxidation method, wherein the electrolyte adopted by the micro-arc oxidation is the electrolyte provided by the invention. Through the method of the invention, a micro-arc oxidation film is formed on the surface of zirconium or zirconium alloy so as to greatly improve the corrosion resistance of the zirconium or zirconium alloy. In addition, the method of the invention also can further improve stain resistance, compactness, hardness, abrasion resistance and electrical insulating property of the zirconium or zirconium alloy surface.