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: This invention provides a method for atomic transformations carried out under conditions akin to chemical catalysis. Liquid and solid state catalysts are used in a two-step process. We have found that the high ionic/electric activity of concentrated sodium hydroxide solution in combination with heating is sufficient to induce atomic transformation and provide a solid phase catalyst of high aluminum and silicon content. This product when heated at a temperature of 1000° C. yields numerous elements of higher atomic masses.

Abstract: A method of fabricating a zirconium alloy flat product, the method being characterized by: preparing or casting a zirconium alloy ingot containing at least 95% by weight of zirconium, and including the usual impurities and alloying elements; shaping said ingot in order to obtain a flat product; subjecting said flat product to a ? quenching operation under conditions that are determined to obtain within the flat product an acicular structure at the end of said ? quenching; subjecting said flat product, after the ? quenching, to a rolling operation performed in a single rolling sequence without intermediate annealing, said rolling being performed at a temperature lying in the range ambient to 200° C., and having a reduction ratio lying in the range 2% to 20%; and subjecting said rolled flat product to an annealing treatment in the a range or in the ?+? range, performed in the temperature range 500° C. to 800° C. for 2 minutes to 10 hours.

Abstract: The invention proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron, from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 80 ppm of carbon, from 5 to 35 ppm of sulphur and less than 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content less 0.5% to the iron content, optionally supplemented by the chromium and/or vanadium content, being lower than 3.

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: Provided is 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 thermo-optically functional composition is disclosed. The composition includes a solid solution of at least two materials selected such that the composition emits thermal radiation, wherein each material is selected from the group consisting of metal carbides, metal nitrides, metal oxides, metal borides, metal silicides and combinations thereof, wherein each metal is selected from the group consisting of tungsten or tungsten alloys, hafnium or hafnium alloys, niobium or niobium alloys, tantalum or tantalum alloys, titanium or titanium alloys, zirconium or zirconium alloys, and combinations of two or more thereof.

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: A method for in-gas micro/nanoimprinting of bulk metallic glass includes steps of preparing a die, heating the bulk metallic glass and in-gas micro/nanoimprinting of the bulk metallic glass. In the step of preparing a die, the die has a micro/nano structure having multiple depressions and a flow channel connected to the depressions. In the step of heating the bulk metallic glass, the bulk metallic glass is heated to a temperature between a glass transition temperature and a crystallization temperature of the bulk metallic glass. In the step of in-gas micro/nanoimprinting, the bulk metallic glass is forced into the die in presence of gas to imprint a complementing micro/nano structure on the bulk metallic glass. Because the die has a flow channel to allow air or gas to escape from the micro/nano structure of the die, the micro/nanoimprinting can be performed in presence of air or gas.

Abstract: The alloy contains, by weight, at least 95% zirconium and from 0.01 to 0.1% sulphur and, optionally, at least one element from the group consisting of the elements tin, iron, chromium, hafnium, niobium, nickel, oxygen and vanadium, the balance of the alloy consisting of inevitable impurities. The sulphur is present in the alloy in the dissolved state, thereby improving the creep strength and in the form of uniformly distributed fine precipitates, thereby improving the corrosion and hydriding resistance. The alloy may be heated by a solution annealing treatment in the ? phase followed by a quench or by a soak at a temperature below 950° C. in order to transform it into the ? or ?+? phase.

Abstract: An amorphous alloy member including an irregular region having a center line average roughness Ra of about 0.1 ?m to about 1000 ?m on a surface, at least the irregular region including an amorphous alloy having an amorphous phase at a volume ratio of about 50% to about 100%. A process for manufacturing the amorphous alloy member, and an authenticity determination device and an authenticity determination method using the amorphous alloy member.

Abstract: A zirconium-based alloy, suitable for use in a corrosive environment, where it is subjected to increased radiation and comprises 0.5-1.6 percentage by weight Nb and 0.3-0.6 percentage by weight Fe. The alloy is characterised in that it comprises 0.5-0.85 percentage by weight Sn.

Abstract: A titanium alloy obtained by a cold-working step, in which 10% or more of cold working is applied to a raw titanium alloy, comprising a Va group element and the balance of titanium substantially, and an aging treatment step, in which a cold-worked member, obtained after the cold-working step, is subjected to an aging treatment so that the parameter “P” falls in a range of from 8.0 to 18.5 at a treatment temperature falling in a range of from 150° C. to 600° C.; and characterized in that its tensile elastic limit strength is 950 MPa or more and its elastic deformation capability is 1.6% or more. This titanium alloy is of high elastic deformation capability as well as high tensile elastic limit strength, and can be utilized in a variety of products extensively.

Abstract: A fuel element for a pressurized water reactor is described. The fuel element contains a laterally open skeleton having control-rod guide tubes each with a first end and a second end, spacers fastened to the control-rod guide tubes, a fuel element head disposed at the first end of the control-rod guide tubes, and a fuel element foot disposed at the second end of the control-rod guide tubes. Gastight cladding tubes are inserted into the skeleton and each is filled with a column of fuel pellets. At least some of the gastight cladding tubes have a multilayer wall. The multilayer wall is formed of a mechanically stable matrix containing a first zirconium alloy disposed in a middle of the multiplayer wall; and a thinner protective layer of a second zirconium alloy alloyed to a lesser extent than the first zirconium alloy. The thinner protective layer is bound metallurgically to the matrix and is disposed on an inside of the matrix facing the fuel pellets.

Abstract: A titanium alloy member is characterized in that it comprise 40% by weight or more titanium (Ti), a IVa group element and/or a Va group element other than the titanium, wherein a summed amount including the IVa group element and/or the Va group element as well as the titanium is 90% by weight or more, and one or more members made in an amount of from 0.2 to 2.0% by weight and selected from an interstitial element group consisting of oxygen, nitrogen and carbon, and that its basic structure is a body-centered tetragonal crystal or a body-centered cubic crystal in which a ratio (c/a) of a distance between atoms on the c-axis with respect to a distance between atoms on the a-axis falls in a range of from 0.9 to 1.1. This titanium alloy member has such working properties that conventional titanium alloys do not have, is flexible, exhibits a high strength, and can be utilized in a variety of products.

Abstract: A fuel element for a pressurized water reactor is described. The fuel element contains a laterally open skeleton having control-rod guide tubes each with a first end and a second end, spacers fastened to the control-rod guide tubes, a fuel element head disposed at the first end of the control-rod guide tubes, and a fuel element foot disposed at the second end of the control-rod guide tubes. Gastight cladding tubes are inserted into the skeleton and each is filled with a column of fuel pellets. At least some of the gastight cladding tubes have a multilayer wall. The multilayer wall is formed of a mechanically stable matrix containing a first zirconium alloy disposed in a middle of the multiplayer wall; and a thinner protective layer of a second zirconium alloy alloyed to a lesser extent than the first zirconium alloy. The thinner protective layer is bound metallurgically to the matrix and is disposed on an inside of the matrix facing the fuel pellets.

Abstract: The alloy contains, by weight, at least 95% zirconium and from 0.01 to 0.1% sulphur and, optionally, at least one element from the group consisting of the elements tin, iron, chromium, hafnium, niobium, nickel, oxygen and vanadium, the balance of the alloy consisting of inevitable impurities. The sulphur is present in the alloy in the dissolved state, thereby improving the creep strength and in the form of uniformly distributed fine precipitates, thereby improving the corrosion and hydriding resistance. The alloy may be heated by a solution annealing treatment in the ? phase followed by a quench or by a soak at a temperature below 950° C. in order to transform it into the ? or ?+? phase.

Abstract: The invention proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron having from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content, less 0.5%, to the iron content, optionally supplemented by the chromium and/or vanadium content.

Abstract: The present invention relates to high-purity zirconium or hafnium with minimal impurities, particularly where the content of alkali metal elements such as Na, K; radioactive elements such as U, Th; transitional metals or heavy metals or high melting point metal elements such as Fe, Ni, Co, Cr, Cu, Mo, Ta, V; and gas components such as C, O, etc. is extremely reduced, as well as to an inexpensive manufacturing method of such high-purity zirconium or hafnium, thereby reducing the impurities hindering the guarantee of the operational performance of semiconductors. The present invention further relates to an inexpensive and safe manufacturing method of high-purity zirconium or hafnium powder from hydrogenated high-purity zirconium or hafnium powder.

Abstract: The invention encompasses methods of forming titanium-based mixed-metal materials and zirconium-based mixed-metal materials utilizing one or more of a reduction process, electrolysis process and iodide process. The invention also encompasses a sputtering target comprising zirconium and one or more elements selected from the group consisting of Al, B, Ba, Be, Ca, Ce, Co, Cs, Dy, Er, Fe, Gd, Hf, Ho, La, Mg, Mn, Mo, Nb, Nd, Ni, Pr, Sc, Sm, Sr, Ta, Ti, V, W, Y, and Yb. The invention also encompasses a sputtering target comprising titanium and boron.

Abstract: Various elements and alloys selected to achieve both biocompatibility and low melting point for use in infiltrating a porous matrix. The infiltrated porous matrix may be made of ceramic, metal, bioglass, or other suitable material. The infiltrated matrix may be used as a biomedical implant, such as for bone repair and regeneration. The matrix may be manufactured using solid free form fabrication techniques such as three-dimensional printing.

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: This present invention relates to an alloy comprising Sn, at least one of Ti and Zr and at least one of Nb and Ta as the major elements. The total percentage of the Nb and Ta in the alloy material is preferably from 8 to 20 atom % and the percentage of the Sn in the alloy material is preferably from 2 to 6 atom %. The alloy material is preferably Ni-free and has shape memory characteristics or superelasticity.

Abstract: The present invention relates to a hafnium silicide target for forming a gate oxide film composed of HfSi1.02-2.00. Obtained is a hafnium silicide target superior in workability and embrittlement resistance, and suitable for forming a HfSiO film and HfSiON film that may be used as a high dielectric gate insulation film in substitute for a SiO2 film, and to the manufacturing method thereof.

Abstract: A zirconium-based alloy for the components of the active core of nuclear reactors comprises (on a weight percent basis): niobium, 0.5-3.0; iron, 0.005-0.5; oxygen, 0.03-0.2; carbon, 0.001-0.04; silicon, 0.002-0.1; nickel, 0.003-0.02; zirconium being the balance; the alloy structure is characterized by an &agr;-solid solution and the &bgr; Nb-phase particles sized below 0.1 &mgr;m and having the niobium content of from 60 to 95%. The alloy may further comprise particles of intermetallics Zr—Fe—Nb with the Fe/Nb ratio of 0.05-0.2. The alloy structure may also be characterized by an oxygen-hardened &agr;-solid solution and by the &bgr; Nb-phase particles, and may further comprise particles of intermetallics Zr—Fe—Nb sized below 0.3 &mgr;m.

Abstract: The active brazing solder for brazing ceramic parts of alumina, particularly of high-purity alumina, contains a maximum of 12 wt. % Ti, a maximum of 8 wt. % Be, and less than 16.5 wt. % Fe, the remainder being Zr and any impurities that may be present. The active brazing solder has the following behaviour/features: Brazing temperature: lower than 1,000° C.; the brazed joint is high-vacuum-tight over a long period of time; the coefficient of thermal expansion of the active brazing alloy is substantially identical to that of the alumina ceramic in the entire temperature range covered during the brazing process; the strength of the brazed joint between the two ceramic parts is so high that under tensile loading, fracture will result not at the joint, but in the adjacent ceramic; the pressure resistance of the active brazing solder is greater than 2 GPa; the active brazing solder is very good processable into powders having particle sizes on the order of 10 &mgr;m.

Abstract: A metal frame for electronic hardware and a method of manufacturing such a frame wherein at least a portion of the frame is made of bulk-solidifying amorphous alloys or bulk-solidifying amorphous alloy-composites is provided. The metal frames of the invention are preferably made of bulk-forming amorphous alloys or bulk-forming amorphous alloy-composites having an elastic limit for the metal frame of at least about 1.5%, and preferably greater than about 2.0%, a &Dgr;Tsc of more than 30° C., and at least one of the following properties: a hardness value of about 4 GPA or more, and preferably 5.5 GPA or more; a yield strength of about 2 GPa or more; a fracture toughness of about 10 ksi-sqrt(in) (sqrt:squre root) or more, and preferably 20 ksi sqrt(in) or more; and a density of at least 4.5 g/cc or more.

Abstract: A Ti—Zr type alloy manifesting excellent plastic workability at normal temperature fit for the use in general industry, allowing improvement in corrosion resistance fit for the use in medical treatment, offering improved corrosion resistance in an acidic solution, particularly a HCl solution, and having flexibility as evinced by a low Young's modulus on a par with a bone; and a medical appliance such as a guide wire to be directly inserted into a blood vessel of a human body under the X-ray fluoroscopy and a stent retained in a human body for a long time, which are made of the Ti—Zr type alloy are provided. The Ti—Zr type alloy of the present invention consists of 25 to 50% by weight of Ti, 25 to 60% by weight of Zr, 5 to 30% by weight of Nb, and 5 to 40% by weight of Ta, provided that the weight ratio of Zr to Ti be in the range of 0.5 to 1.5 and the weight ratio of Nb to Ta be in the range of 0.125 to 1.5.

Abstract: Various aspects of the present invention provides a nanocrystalline powder suitable for storing hydrogen and a method of producing such a powder. One embodiment provides a nanocrystalline powder containing crystals of an aluminum alloy selected from the group consisting of NaAlx, LiAlx, and MgAl2x, wherein x is between 0.9 and 1.1, desirably 0.95-1.05, preferably about 1. The nanocrystalline powder also desirably includes an intercalated catalyst selected from the group consisting of C, Ti, Pt, Pd, V, Zr, and combinations of two or more of those materials.

Abstract: The present invention relates to a non-brittle silicide target for forming a gate oxide film made of MSi0.8-1.2 (M: Zr, Hf), and provides a non-brittle silicide target suitable for forming a ZrO2.SiO2 film or HfO2.SiO2 film that can be used as a high dielectric gate insulating film having properties to substitute an SiO2 film.

Abstract: Disclosed herein are zirconium-base alloys excellent in both corrosion resistance and hydrogen absorption property, useful as materials for nuclear reactors. Such a zirconium-base alloy for nuclear reactors comprises 0.5-2 wt. % Sn, 0.07-0.6 wt. % Fe, 0.03-0.2 wt. % Ni, 0.05-0.2 wt. % Cr, and the balance being zirconium and unavoidable impurities, wherein the Fe content (X wt. %) of the zirconium-base alloy and the mean size (Y nm) of precipitates in the zirconium-base alloy are present in a region on the x (Fe content X) and y (mean precipitate size) rectangular coordinates, surrounded by the following five lines: i) Y=−444×X+154, ii) Y=910×X−46, iii) Y=0, iv) Y=300, and v) X=0.6.

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: Improved bulk-solidifying amorphous alloy compositions and methods of making and casting such compositions are provided. The improved bulk-solidifying amorphous alloys are preferably subjected to a superheating treatment and subsequently are cast into articles with high elastic limit. The invention allows use of lower purity raw-materials, and as such effectively reduces the overall cost of the final articles. Furthermore, the invention provides for the casting of new alloys into shapes at lower cooling rates then is possible with the conventional bulk-solidifying amorphous alloys.

Abstract: This invention relates to a high temperature melting composition and a method of using the composition for brazing high temperature niobium-based substrates, such as niobium-based refractory metal-intermetallic compositions (RMIC), including but not restricted to niobium-silicide composite alloys. The high temperature melting composition can include one or more alloys. The alloys include a base element selected from titanium, tantalum, niobium, hafnium, silicon, and germanium. The alloys also include at least one secondary element that is different from the base element. The secondary element can be selected from chromium, aluminum, niobium, boron, silicon, germanium and mixtures thereof. When two or more alloys are included in the composition, it is preferable, but not required, to select at least one lower melting alloy and at least one higher melting alloy. The composition is preferably a homogeneous mixture of the two or more alloys combined in powder form.

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: Non-evaporable getter alloys containing zirconium, vanadium, iron, manganese and one or more elements selected among yttrium, lanthanum and Rare Earths are described, having improved features of gas sorption, particularly of nitrogen, with respect to the known getter alloys.

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

Abstract: Non-evaporable getter alloys containing zirconium, vanadium, iron, manganese and one or more elements selected among yttrium, lanthanum and Rare Earths are described, having improved features of gas sorption, particularly of nitrogen, with respect to the known getter alloys.

Abstract: The present invention relates to high oxygen ion conducting/oxygen storage (OIC/OS) materials, a catalyst employing the OIC/OS materials, and a method for converting hydrocarbons, carbon monoxide and nitrogen oxides using the catalyst. The OIC/OS materials have significantly higher oxygen storage capacity than that predicted based on Ce content due to the unexpected high and facile redox activity of the added niobium. These materials are further characterized by having a tetragonal crystalline structure under oxidizing conditions (in air) up to about 1,200° C. and a cubic crystalline structure in reducing conditions (5% hydrogen) up to about 1,000° C. for 24 hours. These materials comprise, based upon 100 mole % of the metal component in the material, up to about 95 mole % zirconium, up to about 50 mole % cerium, about 0.5 to about 15 mole % rare earth metal(s), alkaline earth metal(s) or a combination thereof, and about 0.5 to about 15 mole % niobium.

Abstract: A hydrogen storage alloy, represented by the following formula I which is suitable for use as an active anode material for ni-metal hydride secondary cells by virtue of its high discharge characteristics including, for example, a discharge capacity ranging from approximately 300 to 400 mAh/g and a rate capability of at least 80%; Zr1−xtix(MnuVvNiy)z  I wherein, x, u, v, and z each represent an atom fraction under the condition of: 0<x≦0.2, 1.5≦u≦0.7, 0.5≦v≦0.7, 1.0≦y≦1.4, and 0.84≦z≦1.0.1.

Abstract: The active brazing solder for brazing ceramic parts of alumina, particularly of high-purity alumina, contains a maximum of 12 wt. % Ti, a maximum of 8 wt. % Be, and less than 16.5 wt. % Fe, the remainder being Zr and any impurities that may be present. The active brazing solder has the following behaviour/features: Brazing temperature: lower than 1,000 ° C.; the brazed joint is high-vacuum-tight over a long period of time; the coefficient of thermal expansion of the active brazing alloy is substantially identical to that of the alumina ceramic in the entire temperature range covered during the brazing process; the strength of the brazed joint between the two ceramic parts is so high that under tensile loading, fracture will result not at the joint, but in the adjacent ceramic; the pressure resistance of the active brazing solder is greater than 2 GPa; the active brazing solder is very good processable into powders having particle sizes on the order of 10 &mgr;m.

Abstract: A description follows of an article based on a nickel-chromium-silicon metal alloy, including microcrystalline borides, obtained by the rapid solidification and subsequent thermal treatment of a nickel-chromium-boron-silicon metal alloy comprising from 39.0 to 69.4 atom % of nickel, from 11.8 to 33.9 atom % of chromium, from 7.6 to 27.4 atom % of boron and from 7.6 to 17.5 atom % of silicon. The above article is preferably a tape or a sheet or a fiber having high mechanical properties and is particularly resistant to oxidation.

Abstract: The invention includes a method of forming a material which comprises at least two elements. More specifically, the method comprises providing an electrolytic cell comprising a cathode, an anode, and an electrolytic solution extending between the cathode and anode. A metallic product is electrolytically formed within the electrolytic cell. The forming of the metallic product comprises primarily electrorefining of a first element of the at least two elements and primarily electrowinning of a second element of the at least two elements. The invention also includes a mixed metal product comprising at least two elements, such as a product comprising tantalum and titanium.

Abstract: A process is provided for the production of porous non-evaporable getter materials comprising at least one first element selected from Zr and Ti and at least one second element selected from V, Cr, Mn and Ni. The starting metal powders are produced by reduction of the corresponding oxides, with calcium hydride and the thus obtained powders are compacted and sintered at a value of pressure and temperature in a given range. The getter materials due to the production process, have a novel distribution of chemical composition through the getter body, resulting in an improved combination of mechanical and gas-sorption properties.

Abstract: A method for increasing the resistance of zirconium alloy tubing to nodular corrosion by applying a protective anneal at a temperature within a clearly defined temperature range. Also, a zirconium alloy tubing having such protective anneal is disclosed. The protective anneal comprises heating exposed surfaces of zirconium tubing to a temperature range bounded at its lower limit by the temperature Tc, Tc being the temperature which at equilibrium conditions a critical concentration of solute exists in &agr;-matrices of the zirconium alloy to resist nodular corrosion, and bounded at its upper limit by the maximum temperature at which precipitates exist in association with the &agr; and &bgr; matrices in the particular zirconium alloy. In respect of Zircalloy-2 containing zirconium and the following metals by weight, namely 1.2-1.7% tin, 0.13-0.20% iron, 0.06-0.15% chromium, and 0.05-0.08% nickel, the lower temperature limit Tc is approximately 840 C and the upper limit is approximately 855 C.

Abstract: An alloy of zirconium and niobium that includes erbium as a consumable neutron poison, its method of preparation and a component comprising said alloy are provided. This invention relates to an alloy of zirconium and niobium that includes erbium as a consumable neutron poison. The invention also relates to a method for the preparation and conversion of said alloy and a component comprising said alloy. Such an alloy is particularly intended for the manufacture of cladding and/or other elements or structural components of fuel assemblies for nuclear reactors using water as coolant.

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: It is described a process for the production of porous non-evaporable getter materials comprising at least one first element selected between Zr and Ti and at least one second element selected among V, Cr, Mn and Ni, wherein the starting metal powders are produced by reduction with calcium hydride of the corresponding oxides and the thus obtained powders are compacted and sintered at a value of pressure and temperature in a given range; also described are getter materials that, due to the production process, have a novel distribution of chemical composition through the getter body resulting in an improved combination of mechanical and gas-sorption properties.

Abstract: High strength zirconium alloys with improved strength and creep resistance having 1.5 to 6 weight percent bismuth and an element or mixtures of elements selected from the group of molybdenum, tin and niobium.

Abstract: Dental and orthodontic articles comprising alloys of a material selected from the group consisting of T, Zr, Si, Mo, Co, Nb and Be. The alloys may further include at least one secondary alloying element selected from the group consisting of Ta, Cr, Al, V, Pd, Hf and Fe. The alloys preferably comprise a primary constituent in the range of about 30-85% by weight of the alloy, a secondary alloying component in the range of about 0.5-10% by weight, and the alloy has a modulus of elasticity in the range of about 5 million to 15 million psi.