Abstract: An alloy according to example embodiments of the present invention may include zirconium, tin, iron, chromium, and nickel, with a majority of the alloy being zirconium. The composition of the alloy may be about 0.85-2.00% tin by weight, about 0.15-0.30% iron by weight, about 0.40-0.75% chromium by weight, and less than 0.01% nickel by weight. The alloy may further include 0.004-0.020% silicon by weight, 0.004-0.020% carbon by weight, and/or 0.05-0.20% oxygen by weight. Accordingly, the alloy exhibits reduced hydrogen absorption and improved corrosion resistance and may be used to form a fuel assembly component.

Abstract: A method for surface processing at least a portion of a component of zirconium or hafnium alloy, including at least one operation of nanostructuring a surface layer of the alloy so as to confer on the alloy over a thickness of at least 5 ?m a grain size which is less than or equal to 100 nm, the nanostructuring being carried out at a temperature which is less than or equal to that of the last thermal processing operation to which the component was previously subjected during its production. Component of zirconium or hafnium alloy processed in this manner.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.

Abstract: Identifying a stable phase of a binary alloy comprising a solute element and a solvent element. In one example, at least two thermodynamic parameters associated with grain growth and phase separation of the binary alloy are determined, and the stable phase of the binary alloy is identified based on the first thermodynamic parameter and the second thermodynamic parameter, wherein the stable phase is one of a stable nanocrystalline phase, a metastable nanocrystalline phase, and a non-nanocrystalline phase.

Abstract: Disclosed is a zirconium alloy material having high corrosion resistance regardless of thermal history during its manufacturing process. The zirconium alloy material is obtained by providing a zirconium alloy containing on the mass basis: 0.001% to 1.9% of Sn, 0.01% to 0.3% of Fe, 0.01% to 0.3% of Cr, 0.001% to 0.3% of Ni, 0.001% to 3.0% of Nb, 0.027% or less of C, 0.025% or less of N, 4.5% or less of Hf and 0.16% or less of O with the remainder being inevitable impurities and zirconium, being formed of a bulk alloy and a surface layer, in which the surface layer has a plastic strain of 3 or more or a Vickers hardness of 260 HV or more and an arithmetic mean surface roughness Ra of 0.2 ?m or less.

Abstract: Getter devices based on powders of alloys particularly suitable for hydrogen and nitrogen sorption are described. Such alloys have a composition including zirconium, vanadium, titanium and, optionally, one or more elements selected from iron, chromium, manganese, cobalt, nickel and aluminum.

Abstract: In a dry etching method for etching a metal film formed on a substrate by use of etching gas containing ?-diketone, the metal film contains at least one metal material that forms a penta- or hexa-coordinated complex structure with ?-diketone; the etching gas containing ?-diketone contains at least one additive among H2O or H2O2; and the additive is contained at a volume concentration of 1% or greater and 20% or less.

Abstract: Provided in one embodiment is a method of identifying a stable phase of an ordering binary alloy system comprising a solute element and a solvent element, the method comprising: determining at least three thermodynamic parameters associated with grain boundary segregation, phase separation, and intermetallic compound formation of the ordering binary alloy system; and identifying the stable phase of the ordering binary alloy system based on the first thermodynamic parameter, the second thermodynamic parameter and the third thermodynamic parameter by comparing the first thermodynamic parameter, the second thermodynamic parameter and the third thermodynamic parameter with a predetermined set of respective thermodynamic parameters to identify the stable phase; wherein the stable phase is one of a stable nanocrystalline phase, a metastable nanocrystalline phase, and a non-nanocrystalline phase.

Abstract: Provided is a super elastic alloy for biological use having a high biocompatibility, good processability and super elasticity, said super elastic alloy being a super elastic zirconium alloy for biological use comprising 27-54 mol % inclusive of titanium, 5-9 mol % inclusive of niobium which is a ? phase-stabilizing element capable of stabilizing the ? phase of zirconium, and 1-4 mol % inclusive in total of tin and/or aluminum which are ? phase-suppressing elements capable of suppressing the ? phase of zirconium, with the balance consisting of zirconium and inevitable impurities.

Abstract: Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350° C. to 750° C., and a second additive having a solubility in zirconium over the temperature range extending from 350° C. to 750° C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350° C. to 750° C. and a solubility of the second additive in the first additive over the temperature range extending from 350° C. to 750° C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350° C. to 750° C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

Abstract: A method and a device are described for the production of metal powder or alloy powder of a moderate grain sizes less than 10 ?m, comprising or containing at least one of the reactive metals zirconium, titanium, or hafnium, by metallothermic reduction of oxides or halogenides of the cited reactive metals with the aid of a reducing metal, wherein said metal powder or alloy powder is phlegmatized by adding a passivating gas or gas mixture during and/or after the reduction of the oxides or halogenides and/or is phlegmatized by adding a passivating solid before the reduction of the oxides or halogenides, wherein both said reduction and also said phlegmatization are performed in a single gas-tight reaction vessel which can be evacuated.

Abstract: Semiconductor structures are provided comprising a substrate and a epitaxial layer formed over the substrate, wherein the epitaxial layer comprises B; and one or more element selected from the group consisting of Zr, Hf and Al and has a thickness greater than 50 nm. Further, methods for integrating Group III nitrides onto a substrate comprising, forming an epitaxial buffer layer of a diboride of Zr, Hf, Al, or mixtures thereof, over a substrate; and forming a Group III nitride layer over the buffer layer, are provided which serve to thermally decouple the buffer layer from the underlying substrate, thereby greatly reducing the strain induced in the semiconductor structures upon fabrication and/or operation.

Abstract: A hydrogen storage alloy having a higher electrochemical hydrogen storage capacity than that predicted by the alloy's gaseous hydrogen storage capacity at 2 MPa. The hydrogen storage alloy may have an electrochemical hydrogen storage capacity 5 to 15 times higher than that predicted by the maximum gaseous phase hydrogen storage capacity thereof. The hydrogen storage alloy may be selected from alloys of the group consisting of A2B, AB, AB2, AB3, A2B7, AB5 and AB9. The hydrogen storage alloy may further be selected from the group consisting of: a) Zr(VxNi4.5-x); wherein 0<x?0.5; and b) Zr(VxNi3.5-x); wherein 0<x?0.9.

Abstract: The invention relates to biodegradable iron alloy-containing compositions for use in preparing medical devices. In addition, biodegradable crystalline and amorphous compositions of the invention exhibit properties that make them suitable for use as medical devices for implantation into a body of a patient. The compositions include elemental iron and one or more elements selected from manganese, magnesium, zirconium, zinc and calcium. The compositions can be prepared using a high energy milling technique. The resulting compositions and the devices formed therefrom are useful in various surgical procedures, such as but not limited to orthopedic, craniofacial and cardiovascular.

Abstract: Zr—Ti—Ni(Cu)-based filler alloy composition having low melting point for brazing titanium and titanium alloys is expressed as: ZraTibNic (Formula 1) where a, b and c denote atomic % of Zr, Ti and Ni, respectively; 47?a?52; 24?b?30; 22?c?26; and 0.3<c/(a+c)<0.35, or ZraTibNicCud (Formula 2) where a, b, c and d denote atomic % of Zr, Ti, Ni and Cu respectively; 48?a?60; 20?b?28; 19?c+d?30; 3?d?12; and 0.12<d/(c+d)?0.5. Including Zr(Ti) solid solution phase as major constituent phase, the alloy compositions have lower liquidus temperature than those of conventional alloys and they include a little amount of Cu or does not include it at all. When the alloy is used as filler alloy for brazing titanium and titanium alloys, brazing can be performed at remarkably low temperature. This can inhibit the microstructure of titanium base metal from changing and being damaged, keeping the titanium base metal preserving inherent properties after brazing.

Abstract: Precursors suitable for chemical vapor deposition, especially ALD, of hafnium oxide or zirconium oxide, have the general formula: (R1Cp)2MR2 wherein Cp represents a cyclopentadienyl ligand, R1 is H or a substituting alkyl group, alkoxy group or amido group of the Cp ligand, R2 is an alkyl group, an alkoxy group or an amido group and M is hafnium or zirconium.

Abstract: Semiconductor structures are provided comprising a substrate and a epitaxial layer formed over the substrate, wherein the epitaxial layer comprises B; and one or more element selected from the group consisting of Zr, Hf and Al and has a thickness greater than 50 nm. Further, methods for integrating Group III nitrides onto a substrate comprising, forming an epitaxial buffer layer of a diboride of Zr, Hf, Al, or mixtures thereof, over a substrate; and forming a Group III nitride layer over the buffer layer, are provided which serve to thermally decouple the buffer layer from the underlying substrate, thereby greatly reducing the strain induced in the semiconductor structures upon fabrication and/or operation.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety.

Abstract: Disclosed is Zr—Ti—Ni(Cu)-based filler alloy composition having low melting point for brazing titanium and titanium alloys. The Zr—Ti—Ni(Cu)-based alloy composition is expressed as: ZraTibNic (Formula 1) where a, b and c denote atomic % of Zr, Ti and Ni, respectively; 47?a?52; 24?b?30; 22?c?26; and 0.3<c/(a+c)<0.35, or ZraTibNicCud (Formula 2) where a, b, c and d denote atomic % of Zr, Ti, Ni and Cu respectively; 48?a?60; 20?b?28; 19?c+d?30; 3?d?12; and 0.12<d/(c+d)?0.5. Including Zr(Ti) solid solution phase as its major constituent phase, the alloy compositions of this invention have lower liquidus temperature than those of conventional alloys and they include a little amount of Cu or does not include it at all. When alloy of the present invention is used as filler alloy for brazing titanium and titanium alloys, brazing can be performed at remarkably low temperature.

Abstract: An coated article includes a substrate; and a coating deposited on the substrate, wherein the coating being a zirconium layer co-doped with M and R. M is at least one element selected from a group consisting of iron, cobalt, nickel, copper, niobium, hafnium and tantalum. R is at least one element selected from a group consisting of scandium, yttrium and lanthanide.

Abstract: A process for recovering metal from a process material comprising the metal and a component that is more volatile than the metal, which process comprises: transporting the process material in a retort provided in a furnace, the retort being operated under vacuum and at a temperature sufficient to cause sublimation of the component from the process material thereby producing purified metal; depositing the component that has been sublimed on a cool surface; removing purified metal from the retort; and removing deposited component from the cool surface.

Abstract: A metallic material is made from at least one refractory metal or an alloy based on at least one refractory metal. The metallic material has an oxygen content of about 1,000 to about 30,000 ?g/g and the oxygen is interstitial.

Abstract: Zr—Ti—Ni(Cu)-based filler alloy composition having low melting point for brazing titanium and titanium alloys is expressed as: ZraTibNic (Formula 1) where a,b and c denote atomic % of Zr, Ti and Ni, respectively; 47?a?52; 24?b?30; 22?c?26; and 0.3<c/(a+c)<0.35, or ZraTibNicCud (Formula 2) where a,b,c and d denote atomic % of Zr, Ti, Ni and Cu respectively; 48?a?60; 20?b?28; 19?c+d?30; 3?d?12; and 0.12<d/(c+d)?0.5. Including Zr(Ti) solid solution phase as major constituent phase, the alloy compositions have lower liquidus temperature than those of conventional alloys and they include a little amount of Cu or does not include it at all. When the alloy is used as filler alloy for brazing titanium and titanium alloys, brazing can be performed at remarkably low temperature. This can inhibit the microstructure of titanium base metal from changing and being damaged, keeping the titanium base metal preserving inherent properties after brazing.

Abstract: Provided is a method of manufacturing high-purity hafnium by using a hafnium sponge with reduced zirconium as the raw material in which the impurity content of Fe, Cr, and Ni, the impurity content of Ca, Na, and K, the impurity content of Al, Co, Cu, Ti, W, and Zn, the alpha dose, the impurity content of U and Th, the impurity content of Pb and Bi, and the content of C as a gas component contained in the hafnium are reduced. Based on this efficient and stable manufacturing technology, additionally provided are a high-purity hafnium material obtained from the foregoing high-purity hafnium, as well as a sputtering target, a gate insulation film and a metal gate thin film, which are formed from this material. This high-purity hafnium has a purity 6N or higher except Zr and gas components, wherein Fe, Cr and Ni are respectively 0.2 ppm or less, Ca, Na and K are respectively 0.1 ppm or less, and Al, Co, Cu, Ti, W and Zn are respectively 0.1 ppm or less.

Abstract: A hafnium alloy target containing either or both of Zr and Ti in a gross amount of 100 wtppm-10 wt % in Hf, wherein the average crystal grain size is 1-100 ?m, the impurities of Fe, Cr and Ni are respectively 1 wtppm or less, and the habit plane ratio of the plane {002} and three planes {103}, {014} and {015} lying within 35° from {002} is 55% or greater, and the variation in the total sum of the intensity ratios of these four planes depending on locations is 20% or less. As a result, obtained is a hafnium alloy target having favorable deposition property and deposition speed, which generates few particles, and which is suitable for forming a high dielectric gate insulation film such as HfO or HfON film, and the manufacturing method thereof.

Abstract: Methods for producing zirconium strips that demonstrate improved formability are disclosed. The zirconium strips of the present disclosure have a purity and crystalline microstructure suitable for improved formability, for example, in the manufacture of certain articles such as panels for plate heat exchangers and high performance tower packing components. Other embodiments disclosed herein relate to formed substantially pure zirconium strip, articles of manufacture produced from the substantially pure zirconium strip, and methods for making the articles of manufacture.

Abstract: A hafnium alloy target containing either or both of Zr and Ti in a gross amount of 100 wtppm-10 wt % in Hf, wherein the average crystal grain size is 1-100 ?m, the impurities of Fe, Cr and Ni are respectively 1 wtppm or less, and the habit plane ratio of the plane {002} and three planes {103}, {014} and {015} lying within 35° from {002} is 55% or greater, and the variation in the total sum of the intensity ratios of these four planes depending on locations is 20% or less. As a result, obtained is a hafnium alloy target having favorable deposition property and deposition speed, which generates few particles, and which is suitable for forming a high dielectric gate insulation film such as HfO or HfON film, and the manufacturing method thereof.

Abstract: Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350° C. to 750° C., and a second additive having a solubility in zirconium over the temperature range extending from 350° C. to 750° C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350° C. to 750° C. and a solubility of the second additive in the first additive over the temperature range extending from 350° C. to 750° C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350° C. to 750° C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

Abstract: Nanomaterial preparation methods, compositions, and articles are disclosed and claimed. Such methods can provide nanomaterials with improved morphologies relative to previous methods. Such materials are useful in electronic applications.

Abstract: Provided is a sputtering target in which the ratio of X-ray intensity of (110) measured with X-ray diffraction is 0.4 or less, and even 0.2 or less in a Ta or Ta alloy target. Further provided is a sputtering target in which the ratio of X-ray intensity of (110) on a Ta or Ta alloy target surface measured with X-ray diffraction is 0.8 or less, and the ratio of the foregoing X-ray intensity at a depth of 100 ?m or deeper is 0.4 or less. This Ta or Ta alloy target is capable of minimizing the fluctuation of the deposition speed for each target throughout the target life of a sputtering target, and thereby improving and stabilizing the production efficiency of semiconductors during the sputtering process, and contributing to the reduction of production costs.

Abstract: Disclosed is a zirconium alloy material having high corrosion resistance regardless of thermal history during its manufacturing process. The zirconium alloy material is obtained by providing a zirconium alloy containing on the mass basis: 0.001% to 1.9% of Sn, 0.01% to 0.3% of Fe, 0.01% to 0.3% of Cr, 0.001% to 0.3% of Ni, 0.001% to 3.0% of Nb, 0.027% or less of C, 0.025% or less of N, 4.5% or less of Hf and 0.16% or less of O with the remainder being inevitable impurities and zirconium, being formed of a bulk alloy and a surface layer, in which the surface layer has a plastic strain of 3 or more or a Vickers hardness of 260 HV or more and an arithmetic mean surface roughness Ra of 0.2 ?m or less.

Abstract: 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 0.6 weight percent iron, and optionally additional alloy elements selected from the group consisting of tin, chromium, copper, vanadium, and nickel with the balance at least 97 weight percent zirconium, including impurities, where a necessary final heat treatment includes one of i) a SRA or PRXA (15-20% RXA) final heat treatment, or ii) a PRXA (80-95% RXA) or RXA final heat treatment.

Abstract: A nanometer-sized porous metallic glass and a method for manufacturing the same are provided. The porous metallic glass includes Ti (titanium) at 50.0 at % to 70.0 at %, Y (yttrium) at 0.5 at % to 10.0 at %, Al (aluminum) at 10.0 at % to 30.0 at %, Co (cobalt) at 10.0 at % to 30.0 at %, and impurities. Ti +Y+Al+Co+the impurities=100.0 at %.

Abstract: Disclosed is Zr—Ti—Ni (Cu)-based filler alloy composition having low melting point for brazing titanium and titanium alloys. The Zr—Ti—Ni (Cu)-based alloy composition is expressed as: ZraTibNic (Formula 1) where a,b and c denote atomic % of Zr, Ti and Ni, respectively; 47<a<52; 24?b?30; 22<c<26; and 0.3<c/(a+c)<0.35, or ZraTibNicCud (Formula 2) where a,b,c and d denote atomic % of Zr, Ti, Ni and Cu respectively; 48?a?60; 20<b<28; 19<c+d<30; 3<d<12; and 0.12<d/(c+d)?0.5. Including Zr(Ti) solid solution phase as its major constituent phase, the alloy compositions of this invention have lower liquidus temperature than those of conventional alloys and they include a little amount of Cu or does not include it at all. When alloy of the present invention is used as filler alloy for brazing titanium and titanium alloys, brazing can be performed at remarkably low temperature.

Abstract: Bulk solidifying amorphous alloys (BMGs) having improved corrosion resistance properties; and more particularly a sub-set of Zr—Ti-based BMGs having improved corrosion resistance properties are provided. The BMG compositions are formed by carefully controlling the concentration of, or removing altogether, highly electronegative elements, such as Ni and Cu from Zr—Ti-based bulk solidifying amorphous alloys thereby producing BMG materials with corrosion resistance properties that far exceed those of current commercially available BMGs and most conventional alloys. The elimination of these electronegative materials also opens the possibility of new uses for BMGs, including in biological applications.

Abstract: The invention concerns an alloy containing equally 0.02 to 0.07% wt. % of the total iron, of chromium or vanadium, 0.8 to 1.3 wt. % of niobium, 100 ppm or less of tin, 1100 to 1700 ppm of oxygen, less than 100 ppm of carbon, 10 to 30 ppm of sulphur and less than 50 ppm of silicon.

Abstract: The invention concerns an alloy containing equally 0.02 to 0.07% wt. % of the total iron, of chromium or vanadium, 0.8 to 1.3 wt. % of niobium, 100 ppm or less of tin, 1100 to 1700 ppm of oxygen, less than 100 ppm of carbon, 10 to 30 ppm of sulphur and less than 50 ppm of silicon.

Abstract: An alloy according to example embodiments of the present invention may include zirconium, tin, iron, chromium, and nickel, with a majority of the alloy being zirconium. The composition of the alloy may be about 0.85-2.00% tin by weight, about 0.15-0.30% iron by weight, about 0.40-0.75% chromium by weight, and less than 0.01% nickel by weight. The alloy may further include 0.004-0.020% silicon by weight, 0.004-0.020% carbon by weight, and/or 0.05-0.20% oxygen by weight. Accordingly, the alloy exhibits reduced hydrogen absorption and improved corrosion resistance and may be used to farm a fuel assembly component.

Abstract: To provide a production process of an electrode catalyst for fuel cell whose initial voltage is high and whose endurance characteristics, especially, whose voltage drop being caused by high-potential application is less. A production process according to the present invention of an electrode catalyst for fuel cell is characterized in that: it includes: a dispersing step of dispersing a conductive support in a solution; a loading step of dropping a platinum-salt solution, a base-metal-salt solution and an iridium-salt solution to the resulting dispersion liquid, thereby loading respective metallic salts on the conductive support as hydroxides under an alkaline condition; and an alloying step of heating the conductive support with metallic hydroxides loaded in a reducing atmosphere to reduce them, thereby alloying them.

Abstract: Oxygen free, solution based zirconium precursors for use in ALD processes are disclosed for growing ZrO2 or other Zr compound films in a self-limiting and conformal manner. An oxygen free, solution based ALD precursor of (t-BuCp)2ZrMC2 is particular useful for depositing ZrO2 or other Zr compound films.

Abstract: The present invention is directed to a process for the preparation of a metal powder having a purity at least as high as the starting powder and having an oxygen content of 10 ppm or less comprising heating said metal powder containing oxygen in the form of an oxide, with the total oxygen content being from 50 to 3000 ppmf in an inert atmosphere at a pressure of from 1 bar to 10?7 to a temperature at which the oxide of the metal powder becomes thermodynamically unstable and removing the resulting oxygen via volatilization. The metal powder is preferably selected from the group consisting of tantalum, niobium, molybdenum, hafnium, zirconium, titanium, vanadium, rhenium and tungsten. The invention also relates to the powders produced by the process and the use of such powders in a cold spray process.

Abstract: Particles and manufacturing methods thereof are provided. The manufacturing method of the particle includes providing a precursor solution containing a precursor dissolved in a solution, and irradiating the precursor solution with a high energy and high flux radiation beam to convert the precursor to nano-particles. Particles with desired dispersion, shape, and size are manufactured without adding a stabilizer or surfactant to the precursor solution.

Abstract: A semiconductor structure and fabrication method is provided for integrating wide bandgap nitrides with silicon. The structure includes a substrate, a single crystal buffer layer formed by epitaxy over the substrate and a group III nitride film formed by epitaxy over the buffer layer. The buffer layer is reflective and conductive. The buffer layer may comprise B an element selected from the group consisting of Zr, Hf, Al. For example, the buffer layer may comprise ZrB2, AlB2 or HfB2. The buffer layer provides a lattice match with the group III nitride layer. The substrate can comprise silicon, silicon carbide (SiC), gallium arsenide (GaAs), sapphire or Al2O3. The group III nitride material includes GaN, AlN, InN, AlGaN, InGaN or AlInGaN and can form an active region. In a presently preferred embodiment, the buffer layer is ZrB2 and the substrate is Si(111) or Si(100) and the group III nitride layer comprises GaN.

Abstract: A method for production of a fuel cladding tube for a nuclear reactor, characterized by the preparation of an ingot of an alloy of zirconium with the following composition by weight %: 0.8%?Nb?2.8%, traces?Sn?0.65%, 0.015%?Fe?0.40%, C?100 ppm, 600 ppm?O?2300 ppm, 5 ppm?S?100 ppm, Cr+V?0.25%, Hf?75 ppm and F?1 ppm the remainder being zirconium and impurities arising from production. The ingot is then subjected to forging, a hardening and thermomoechanical treatments comprising cold laminations separated by intermediate annealing, all intermediate annealings being carried out at a temperature below the ???+? transition temperature of the alloy, finishing with a recrystallization annealing and resulting in the production of a tube, whereupon an optional external cleaning of the tube is carried out and a mechanical polishing of the external surface of the tube is carried out to give a roughness Ra less than or equal to 0.5 ?m. The invention further relates to a fuel cladding tube obtained thereby.

Abstract: Non-evaporable getter alloys are provided which can be activated at relatively low temperatures and are capable of efficiently sorbing hydrogen.

Abstract: 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.

Abstract: A zirconium alloy tube for forming the whole or the outer portion of a nuclear fuel pencil housing or a nuclear fuel assembly guide tube. The zirconium alloy contains 0.8-1.8 wt. % of niobium, 0.2-0.6 wt. % of tin and 0.02-0.4 wt. % of iron, and has a carbon content of 30-180 ppm, a silicon content of 10-120 ppm and an oxygen content of 600-1800 ppm. The tube may be used when recrystallized or stress relieved.