Abstract: Alloys and methods for preparing the same are provided. The alloys are represented by the general formula of (ZraAlbCucNid)100-e-fYeMf, wherein a, b, c, and d are atomic fractions, in which: 0.472?a?0.568; 0.09?b?0.11; 0.27?c?0.33; 0.072?d?0.088; the sum of a, b, c, and d equals 1; e and f are atomic numbers of elements Y and M respectively, in which 0?e?5 and 0.01?f?5; and M is selected from the group consisting of Nb, Ta, Sc, and combinations thereof.

Abstract: A conductive paste including a conductive powder, a metallic glass, and an organic vehicle, wherein the metallic glass has a resistivity that is decreased when the metallic glass is heat treated at a temperature that is higher than a glass transition temperature of the metallic glass.

Abstract: The present disclosure discloses an amorphous alloy composite material comprises an amorphous and continuous matrix phase, and a plurality of equiaxed crystalline phases as reinforcing phases dispersed in the matrix phase. Oxygen content in the amorphous alloy composite material may be less than 2100 ppm. The present disclosure also discloses a method of preparing the same. With the equiaxed crystalline phases dispersed in the matrix phase, the plasticity of the amorphous alloy composite material may be improved considerably.

Abstract: Provided are a crystalline alloy having significantly better thermal stability than an amorphous alloy as well as glass-forming ability, and a method of manufacturing the crystalline alloy. The present invention also provides an alloy sputtering target that is manufactured by using the crystalline alloy, and a method of manufacturing the alloy target. According to an aspect of the present invention, provided is a crystalline alloy having glass-forming ability which is formed of three or more elements having glass-forming ability, wherein the average grain size of the alloy is in a range of 0.1 ?m to 5 ?m and the alloy includes 5 at % to 20 at % of aluminum (Al), 15 at % to 40 at % of any one or more selected from copper (Cu) and nickel (Ni), and the remainder being zirconium (Zr).

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: 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: 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 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 (0); 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: 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: 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: A Zr-based amorphous alloy and a method of preparing the same are provided. The Zr-based amorphous alloy is represented by the general formula of (ZraM1-a)100-xOx, in which a is an atomic fraction of Zr, and x is an atomic percent of 0, in which: 0.3?a?0.9, and 0.02?x?0.6; and M represents at least three elements selected from the group consisting of transition metals other than Zr, Group IIA metals, and Group IIIA metals.

Abstract: An alloy having a formula Zr100-x-u (Cu100-aNia)xAlu wherein X, U and a are in atomic percentages wherein X is less than or equal to 48 and greater than or equal to 37, wherein U is less than or equal to 14 and greater than or equal to 3, and wherein a is less than or equal to ten and greater than or equal to 3. Methods of forming the alloy and bulk metallic glass comprising the alloy are also provided. The alloy and bulk metallic glass are useful in a wide number of applications which includes sports and luxury products, electronic goods, medical instruments, and military equipment.

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: A method of cutting bulk amorphous alloy includes: positioning a target cutting path of the bulk amorphous alloy in an atmosphere of an inert gas; cutting the target cutting path to form a cut surface using a pulsed laser; and removing a plurality of burrs located on the cut surface produced during the cut.

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: An amorphous alloy having the general formula of: (ZrxAlyCuzNi1-x-y-z)100-a-bSCaYb, wherein x, y, and z are atomic percents, and a and b are atom molar ratios, in which: about 0.45?x?about 0.60; about 0.08?y?about 0.12; about 0.25?z?about 0.35; 0<a?about 5; and 0?b<about 0.1.

Abstract: A class of high-density bulk metallic glass hafnium-based alloys, having copper, nickel, aluminum, tin, and titanium or niobium as alloying elements is disclosed. This class includes alloys having higher densities and a higher reduced glass-transition temperature than other known refractory metallic glass alloys.

Abstract: A high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof. Specifically, disclosed are a high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof, the composition comprising: 0.5-1.0 wt % iron; 0.25-0.5 wt % chromium; 0.06-0.18 wt % oxygen; at least one element selected from the group consisting of 0.2-0.5 wt % tin, 0.1-0.3 wt % niobium and 0.05-0.3 wt % copper; and the balance of zirconium. The zirconium alloy has excellent corrosion resistance, and thus can be used as a material for nuclear fuel claddings, spacer grids and nuclear reactor core structures in light water reactor and heavy water reactor nuclear power plants.

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: Alloys and methods of preparing the same are provided. The alloys are represented by the general formula of (ZraMbNc)100-xQx, in which M is at least one transition metal except Zr; N is Be or Al; Q is selected from the group consisting of CaO, MgO, Y2O3, Nd2O3, and combinations thereof; a, b, and c are atomic percents of corresponding elements; and 45?a?75, 20?b?40, 1?c?25, a+b+c=100, and 1?x?15. A method of recycling a Zr-based amorphous alloy waste is also provided.

Abstract: Alloys and methods for preparing the same are provided. The alloys are represented by the general formula of ZraAlbCucNid)100-e-fYeMf, wherein a, b, c, and d are atomic fractions, in which: 0.472?a?0.568; 0.09?b?0.11; 0.27?c?0.33; 0.072?d?0.088; the sum of a, b, c, and d equals 1; e and f are atomic numbers of elements Y and M respectively, in which 0?e?5 and 0.01?f?5; and M is selected from the group consisting of Nb, Ta, Sc, and combinations thereof.

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: Disclosed herein is a zirconium alloy composition for nuclear fuel cladding tubes, comprising: 1.6˜2.0 wt % of Nb; 0.05˜0.14 wt % of Sn; 0.02˜0.2 wt % of one or more elements selected from the group consisting of Fe, Cr and Cu; 0.09˜0.15 wt % of O; 0.008˜0.012 wt % of Si; and a balance of Zr, a nuclear fuel cladding tube comprising the zirconium alloy composition, and a method of manufacturing the nuclear fuel cladding tube. Since the nuclear fuel cladding tube made of the zirconium alloy composition can maintain excellent corrosion resistance by forming a protective oxide film thereon under the conditions of high-temperature and high-pressure cooling water and water vapor, it can be usefully used as a nuclear fuel cladding tube for light water reactors or heavy water reactors, thus improving the economical efficiency and safety of the use of nuclear fuel.

Abstract: A class of high-density bulk metallic glass hafnium alloys, having copper, nickel, aluminum and titanium or niobium as alloying elements is disclosed. This class includes alloys having higher densities and a higher reduced glass-transition temperature than other known metallic glass alloys.

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: An alloy having a formula: (Zr1Ti)100-x-u(Cu100-aNia)XAlu wherein X, U and a are in atomic percentages in the following ranges: 37?x?48, 3?u?14, and 3?a?30.

Abstract: The present invention relates to a zirconium alloy composition having excellent corrosion resistance for nuclear applications and a method of preparing the same. The zirconium alloy composition having excellent corrosion resistance for nuclear applications includes 1.3˜2.0 wt % of niobium, 0.05˜0.18 wt % of iron, 0.008˜0.012 wt % of silicon, 0.008˜0.012 wt % of carbon, and 0.1˜0.16 wt % of oxygen, with the balance being zirconium, or includes 2.8˜3.5 wt % of niobium, 0.2˜0.7 wt % of at least one of iron and copper, 0.008˜0.012 wt % of silicon, 0.008˜-0.012 wt % of carbon, and 0.1˜0.16 wt % of oxygen, with the balance being zirconium.

Abstract: Provided is free cutting alloy excellent in machinability, preserving various characteristics as alloy. The free cutting alloy contains: one or more of Ti and Zr as a metal element component; and C being an indispensable element as a bonding component with the metal element component, wherein a (Ti,Zr) based compound including one or more of S, Se and Te is formed in a matrix metal phase. The free cutting alloy is more excellent in machinability, preserving various characteristics as alloy at similar levels to a conventional case. The effect is especially conspicuous, for example, when a compound expressed in a chemical form of (Ti,Zr)4C2(S,Se,Te)2 as the (Ti,Zr) based compound is formed at least in a dispersed state in the alloy structure.

Abstract: Zirconium-rich bulk metallic glass alloys include quinary alloys containing zirconium, aluminum, titanium, copper and nickel. The bulk metallic glass alloys may be provided as completely amorphous pieces having cross-sectional diameters of at least about 5 mm or even greater.

Abstract: An amorphous alloy having a composition consisting essentially of about 45 to about 65 atomic % Zr and/or Hf, about 4 to about 7.5 atomic % Ti and/or Nb, about 5 to about 15 atomic % Al and/or Zn, and the balance comprising a metal selected from the group consisting of Cu, Co, Ni, up to about 10 atomic % Fe, and Y intentionally present in the alloy composition in an amount not exceeding about 0.5 atomic %, such as about 0.2 to about 0.4 atomic % Y, with an alloy bulk oxygen concentration of at least about 1000 ppm on atomic basis.

Abstract: An amorphous alloy having a composition represented by the formula (Zr,Hf)a(Al,Zn)bTie,Nbf,TagYh(CuxFey(Ni,Co)z)d wherein a ranges from 45 to 65 atomic %, b ranges from 5 to 15 atomic %, e and f each ranges from 0 to 4.5 atomic %, g ranges from greater than 0 to 2 atomic %, h ranges from 0 to 0.5 atomic %, and the balance is d and incidental impurities and wherein e+f+g ranges from 3.5 to 7.5 atomic %, d times y is less than 10 atomic %, and x/z ranges from 0.5 to 2.

Abstract: The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a=0.05-0.4 wt %, b=0.3-0.7 wt %, c=0.1-0.4 wt %, d=0-0.2 wt % and e=0.01-0.2 wt %, provided that Nb+Sn=0.35-1.0 wt %), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at &bgr; phase range, &bgr;-quenching the forged ingot 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 worked ingot at 460-540° C.

Abstract: An amorphous alloy having a composition consisting essentially of about 45 to about 65 atomic % Zr and/or Hf, about 4 to about 7.5 atomic % Ti and/or Nb, about 5 to about 15 atomic % Al and/or Zn, and the balance comprising a metal selected from the group consisting of Cu, Co, Ni, up to about 10 atomic % Fe, and Y intentionally present in the alloy composition in an amount not exceeding about 0.5 atomic %, such as about 0.2 to about 0.4 atomic % Y, with an alloy bulk oxygen concentration of at least about 1000 ppm on atomic basis.

Abstract: A composite metal object comprises ductile crystalline metal particles in an amorphous metal matrix. An alloy is heated above its liquidus temperature. Upon cooling from the high temperature melt, the alloy chemically partitions, forming dendrites in the melt. Upon cooling the remaining liquid below the glass transition temperature it freezes to the amorphous state, producing a two-phase microstructure containing crystalline particles in an amorphous metal matrix. The ductile metal particles have a size in the range of from 0.1 to 15 micrometers and spacing in the range of from 0.1 to 20 micrometers. Preferably, the particle size is in the range of from 0.5 to 8 micrometers and spacing is in the range of from 1 to 10 micrometers. The volume proportion of particles is in the range of from 5 to 50% and preferably 15 to 35%. Differential cooling can produce oriented dendrites of ductile metal phase in an amorphous matrix.

Abstract: An alloy is described that is capable of forming a metallic glass at moderate cooling rates and exhibits large plastic flow at ambient temperature. Preferably, the alloy has a composition of (Zr, Hf)a TabTicCudNieAlf, where the composition ranges (in atomic percent) are 45≦a≦70, 3≦b≦7.5, 0≦c≦4, 3≦b+c≦10, 10≦d≦30, 0≦e≦20, 10≦d+e≦35, and 5≦f≦15. The alloy may be cast into a bulk solid with disordered atomic-scale structure, i.e., a metallic glass, by a variety of techniques including copper mold die casting and planar flow casting. The as-cast amorphous solid has good ductility while retaining all of the characteristic features of known metallic glasses, including a distinct glass transition, a supercooled liquid region, and an absence of long-range atomic order. The alloy may be used to form a composite structure including quasi-crystals embedded in an amorphous matrix.

Abstract: A Zr-based bulk metallic glass formed using low purity materials at a low vacuum with a small amount of yttrium addition is provided. A method of improving the glass forming ability, crystallization and melting process without reducing the mechanical and elastic properties, such as hardness and Young's Modulus, of Zr-based alloys by yttrium addition, is also provided.

Abstract: Changing characteristics of relationships between components of a bulk metallic glass to stabilize one phase relative to another. A specific Zr58.47Nb2.76Cu15.4Ni12.6Al10.37alloy is disclosed.

Abstract: 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.

Abstract: High strength zirconium alloys with improved strength and creep resistance having 1.5 to 6 weight percent bismuth, and niobium.

Abstract: The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows: niobium in a range of 0.15 to 0.25 wt. %; tin in a range of 1.10 to 1.40 wt. %; iron in a range of 0.35 to 0.45; chromium in a range of 0.15 to 0.25; one element selected from the group consisting of molybdenum, copper and manganese in a range of 0.08 to 0.12 wt. %; oxygen in a range of 0.10 to 0.14 wt. %; and the balance being zirconium.

Abstract: 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.

Abstract: The present invention is directed to an advanced zirconium alloy having superior corrosion resistance and high strength suitable for fuel rod cladding, spacer grids and other structural components in a reactor core of nuclear power plants.

Abstract: An alloy material 4 received in a melting hearth 1 is melted by high-density energy supplied from a heat source 5. The molten alloy is transferred to a forced-cooled die 3 having a cavity 2 defining the profile of a product, and quenched to an amorphous state. The alloy has the composition represented by the general formula of Zr.sub.100-a-b-c A.sub.a B.sub.b C.sub.c, wherein the mark A represents one or more elements selected from Ti, Hf, Al and Ga, the mark B represents one or more elements selected from Fe, Co, Ni and Cu, the mark C represents one or more elements selected from Pd, Pt, Au and Ag, and the marks a-c represent the atomic ratios of respective elements A-C under the conditions of a=5-20, b=15-45, c.ltoreq.10 and a+b+c=30-70. The differential temperature region .DELTA.T (=T.sub.x -T.sub.g) in the supercooled liquid phase of the Zr alloy represented by the difference between the crystallization point T.sub.x and the glass transition point T.sub.g is preferably 100 K or more.

Abstract: The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components as used in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows:niobium(Nb), in a range of 0.05 to 0.3 wt. %;tin(Sn), in a range of 0.8 to 1.6 wt. %;iron(Fe), in a range of 0.2 to 0.4 wt. %;a selected one from the group consisted of vanadium(V), tellurium(Te), antimony(Sb), molybdenum(Mo), tantalum(Ta), and copper(Cu), in a range of 0.05 to 0.20 wt. %;oxygen(O), in a range of 600 to 1400 ppm; andthe balance being zirconium(Zr).

Abstract: At least quinary alloys form metallic glass upon cooling below the glass transition temperature at a rate less than 10.sup.3 K/s. Such alloys comprise zirconium and/or hafnium in the range of 45 to 65 atomic percent, titanium and/or niobium in the range of 4 to 7.5 atomic percent, and aluminum and/or zinc in the range of 5 to 15 atomic percent. The balance of the alloy compositions comprise copper, iron, and cobalt and/or nickel. The composition is constrained such that the atomic percentage of iron is less than 10 percent. Further, the ratio of copper to nickel and/or cobalt is in the range of from 1:2 to 2:1. The alloy composition formula is:(Zr,Hf).sub.a (Al,Zn).sub.b (Ti,Nb).sub.c (Cu.sub.x Fe.sub.y (Ni,Co).sub.z).sub.dwherein the constraints upon the formula are: a ranges from 45 to 65 atomic percent, b ranges from 5 to 15 atomic percent, c ranges from 4 to 7.5 atomic percent, d comprises the balance, d.multidot.y is less than 10 atomic percent, and x/z ranges from 0.5 to 2.

Abstract: At least quaternary alloys form metallic glass upon cooling below the glass transition temperature at a rate less than 10.sup.3 K/s. Such alloys comprise titanium from 19 to 41 atomic percent, an early transition metal (ETM) from 4 to 21 atomic percent and copper plus a late transition metal (LTM) from 49 to 64 atomic percent. The ETM comprises zirconium and/or hafnium. The LTM comprises cobalt and/or nickel. The composition is further constrained such that the product of the copper plus LTM times the atomic proportion of LTM relative to the copper is from 2 to 14. The atomic percentage of ETM is less than 10 when the atomic percentage of titanium is as high as 41, and may be as large as 21 when the atomic percentage of titanium is as low as 24. Furthermore, when the total of copper and LTM are low, the amount of LTM present must be further limited. Another group of glass forming alloys has the formula(ETM.sub.1-x Ti.sub.x).sub.a Cu.sub.b (Ni.sub.1-y Co.sub.y).sub.cwherein x is from 0.1 to 0.3, y.cndot.

Abstract: The present invention relates to the control of grain structure in unalloyed zirconium metal and, more particularly, to the control of grain structure in zirconium metals containing less than 300 parts per million Fe.

Abstract: Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor consist essentially of by weight percent about 0.5 to 2.0 percent thin, about 0.24 to 0.40 percent of a solute composed of copper, nickel and iron, wherein the copper is at least 0.05 percent, and the balance zirconium. Nuclear fuel elements for use in the core of a nuclear reactor have improved corrosion resistant cladding made from these zirconium alloys or composite claddings have a surface layer of the corrosion resistant zirconium alloys metallurgically bonded to the outside surface of a Zircaloy alloy tube. The claddings may contain an inner barrier layer of moderate purity zirconium metallurigcally bonded on the inside surface of the cladding to procide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.