Abstract: A modified Ti—V—Zr—Ni—Mn—Cr electrochemical hydrogen storage alloy which has at least one of the following characteristics: 1) an increased charge/discharge rate capability over that the base Ti—V—Zr—Ni—Mn—Cr electrochemical hydrogen storage alloy; 2) a formation cycling requirement which is reduced to one tenth that of the base Ti—V—Zr—Ni—Mn—Cr electrochemical hydrogen storage alloy; or 3) an oxide surface layer having a higher electrochemical hydrogen storage catalytic activity than the base Ti—V—Zr—Ni—Mn—Cr electrochemical hydrogen storage alloy.

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: A BCC type hydrogen-absorbing alloy, which uses a ferroalloy, is advantageous from the aspect of the production cost and exhibits excellent hydrogen absorption and desorption characteristics due to a fine structure constituted by spinodal decomposition even when the iron component is increased. The hydrogen-absorbing alloy is expressed by the general formula AxVayBz, where A is at least one of Ti and Zr, Va is at least one member of the Group Va elements of the Periodic Table consisting of V, Nb and Ta, and B contains at least Fe and is at least one member selected from the group consisting of Cr, Mn, Co, Ni, Cu, Al, Mo and W, each of x, y and z satisfies the relation, in terms of of the atomic number ratio, 0≦x≦70, 0≦y≦50, x+y+z=100, and x/z=0.25 to 2.0, the phase of the body-centered cubic structure is at least 50% in terms of the phase fraction and its lattice constant is at least 0.2950 nm but not greater than 0.3100 nm.

Abstract: A sputtering target comprising a substrate and a target material formed on the substrate, wherein the target material comprises a metal oxide of the chemical formula MOx as the main component, wherein MOx is a metal oxide which is deficient in oxygen as compared with the stoichiometric composition, and M is at least one metal selected from the group consisting of Ti, Nb, Ta, Mo, W, Zr and Hf, a process for its production, and a method for forming a film having a high refractive index.

Abstract: The invention provides a method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties. The method includes performing hot forging, solution heat treatment, hot extruding, and repeated cycles of annealing and cold rolling of a Zr alloy including, by weight, 0.2 to 1.7% Sn, 0.18 to 0.6% Fe, 0.07 to 0.4% Cr and 0.05 to 1.0% Nb, with the remainder being Zr and incidental impurities, and the incidental nitrogen impurity content being 60 ppm or less, and then performing final stress relief annealing thereon. The annealing is performed at a temperature of 550.degree. C. to 850.degree. C. for 1 to 4 hours such that the accumulated annealing parameter .SIGMA.Ai=.SIGMA.ti.multidot.exp(-40,000/Ti) satisfies relationships -20.ltoreq.log.SIGMA.Ai.ltoreq.-15, and -18-10.multidot.X.sub.Nb .ltoreq.log.SIGMA.Ai.ltoreq.-15-3.75.multidot.(X.sub.Nb -0.

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.degree. 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 .mu.m.

Abstract: A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs comprising a zirconium alloy and closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Grain boundaries in each heat affected zone of the cladding tube, which are adjacent to a bead formed by TIG welding, have structural compositions including 4 to 30% by weight of Nb, and 0.9 to 20% by weight of Fe.

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: 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: Nonevaporable getter alloys containing Zr, Co, and a third component A selected from the rare each metals and mixtures thereof, e.g., mischmetal. A most preferred alloy contains about 80.8 wt % Zr, about 14.2 wt % Co, and about 5 wt % A. These alloys are advantageous because they are suitable for general use, i.e., they have a relatively low activation temperature, are capable of sorbing a wide variety of gases, and minimize the environmental and safety risks associated with known nonevaporable getter alloys.

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.

Abstract: A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Precipitates having grain diameters of 0.01 to 0.5 .mu.m and comprise intermetallic compounds containing Zr, Nb and Fe are present at grain boundaries in the structure of heat affected zones of the cladding tube, the heat affected zone being adjacent to a bead formed by TIG welding.

Abstract: Dental and orthodontic articles comprising alloys of a material selected from the group consisting of Ti, 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.

Abstract: A container packed with a mixture of powders classified respectively into two or at least three particle-size distribution groups which are different in average particle size, the powders comprising a hydrogen absorbing alloy singly or the combination of such an alloy and a substance not absorbing hydrogen. The mixture is at least 0.03 to not greater than 0.50 in the ratio d.sub.2 /d.sub.1 wherein d.sub.1 is the average particle size of the powder having the particle-size distribution of the largest average particle size, and d.sub.2 is the average particle size of the powder having the particle-size distribution of the second largest average particle size. The weight ratio of the powder to the total weight of the powders is greater when that powder has a particle-size distribution of larger average particle size.

Abstract: A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.

Abstract: Zirconium-based components for nuclear reactors are disclosed whereby a rare earth or other metal which preferentially concentrates hydrogen when in contact with zirconium is dispersed as a second phase throughout a zirconium-based matrix. The morphology and distribution of the two-phase material is controlled such that the second phase, internal hydrogen absorbing particles, are provided as spherical particles, randomly distributed, to minimize the effects of the occluded hydrogen.

Abstract: A reinforcement-containing metal-matrix composite material is formed by dispersing pieces of reinforcement material throughout a melt of a bulk-solidifying amorphous metal and solidifying the mixture at a sufficiently high rate that the solid metal matrix is amorphous. Dispersing is typically accomplished either by melting the metal and mixing the pieces of reinforcement material into the melt, or by providing a mass of pieces of the reinforcement material and infiltration of the molten amorphous metal into the mass. The metal preferably has a composition of about that of a eutectic composition, and most preferably has a composition, in atomic percent, of from about 45 to about 67 percent total of zirconium plus titanium, from about 10 to about 35 percent beryllium, and from about 10 to about 38 percent total of copper plus nickel.

Abstract: The present invention provides a zirconium based alloy member which has very small deformation of elongation and bow occurring due to irradiation growth, a method of manufacturing it, and particularly an channel box for an atomic reactor fuel assembly. A zirconium based alloy plate member having a width of not less than 100 mm and a long length, containing not more than 5 wt % Nb and/or not more 5 wt % Sn, the member having (0001) orientation (Fl value) of hexagonal Zr with respect to longitudinal direction ranging from 0.20 to 0.35, the difference in Fl between the middle and the end being not more than the value calculated from (0.0935.times.Fl-0.00585) and an amount of bow at neutron irradiation of 35 GWd/t which bow occurs in the channel box for a reactor being not more than 2.16 mm.

Abstract: Zirconium alloys for use in an aqueous environment subject to high fluence of a water reactor and characterized by improved corrosion resistance, consisting essentially of 0.3 to 1.8 weight percent tin, 0.1 to 0.65 weight percent iron, the balance of alloys being essentially nuclear grade zirconium with incidental impurities and having a microstructure of Zr.sub.3 Fe second phase precipitates distributed uniformly intragranularly and intergranularly to form radiation resistant second phase precipitates in the alloy matrix.

Abstract: Zirconium alloys for use in an aqueous environment subject to high fluence of a water reactor and characterized by improved corrosion resistance, consisting essentially of from 0.5 to 3.25 weight percent niobium, from 0.3 to 1.8 weight percent tin, the balance of alloys being essentially nuclear grade zirconium with incidental impurities and having a microstructure of beta niobium second phase precipitates distributed uniformly intragranularly and intergranularly to form radiation resistant second phase precipitates in the alloy matrix.

Abstract: Disordered multicomponent hydrogen storage material characterized by extraordinarily high storage capacity due to a high density of useable hydrogen storage sites (greater than 10.sup.23 defect sites/cc) and/or an extremely small crystallite size. The hydrogen storage material can be employed for electrochemical, fuel cell and gas phase applications. The material may be selected from either of the modified LaNi.sub.5 or modified TiNi families formulated to have a crystallite size of less than 200 Angstroms and most preferably less than 100 Angstroms.

Abstract: A process for fabricating nuclear fuel rod cladding tube comprising beta quenching a zirconium alloy billet consisting essentially of from 0.5 to 3.25 weight percent niobium, from 0.3 to 1.8 weight percent tin, the balance of the alloy being essentially nuclear grade zirconium with incidental impurities by heating to a temperature in the beta range above 950.degree. C. and rapidly quenching the billet to a temperature below the .alpha. plus .beta. to .alpha. transformation temperature to form a martensitic structure; extruding the beta-quenched billet at a temperature below 600.degree. C. to form a hollow; annealing the hollow by heating at a temperature up to 590.degree. C.; pilgering the annealed hollow; and final annealing the pilgered annealed hollow to a temperature up to 590.degree. C.

Abstract: A process for fabricating nuclear fuel rod cladding tube comprising beta quenching a zirconium alloy billet consisting essentially of 0.3 to 1.8 weight percent tin, 0.1 to 0.65 weight percent iron, the balance of the alloy being essentially nuclear grade zirconium with incidental impurities by heating to a temperature in the beta range greater than about 1000.degree. C. and rapidly quenching the billet to a temperature below the .alpha. plus .beta. to a transformation temperature to form a martensitic structure; extruding the beta-quenched billet at a temperature between 600.degree. and 750.degree. C. to form a hollow; annealing the hollow by heating at a temperature up to about 700.degree. C.; pilgering the annealed hollow; and final annealing the pilgered annealed hollow to a temperature up to about 700.degree. C. to form the nuclear fuel rod cladding tube comprising the alloy having a microstructure of Zr.sub.

Abstract: The alloy has a base composition similar to that of a zirconium alloy of known type used for the manufacture of an element intended for use in the core of a nuclear reactor, such as a cladding tube, a guide tube, or another structural element of a fuel assembly. In addition, the alloy contains sulphur in a proportion by weight of between 8 and 100 ppm and preferably between 8 and 30 ppm.

Abstract: A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 0.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.

Abstract: A fuel assembly for a pressurized water reactor having a fuel rod with a high strength cladding tube including an inner tubular layer of a zirconium alloy with alloying components of molybdenum and 3 to 6 weight percent bismuth, the balance zirconium.

Abstract: A torsionally reacting spring, such as a helical spring, a torsion bar, or a torsion tube, requires the ability to torsionally deform elastically during service and return to its original, undeformed shape. The torsionally reacting spring is made of a bulk-deforming amorphous alloy which may be cooled from the melt at a cooling rate of less than about 500.degree. C. per second, yet retain an amorphous structure. A preferred bulk-solidifying amorphous alloy has a composition, in atomic percent, of from about 45 to about 67 percent total of zirconium plus titanium, from about 10 to about 35 percent beryllium, and from about 10 to about 38 percent total of copper plus nickel, plus incidental impurities, the total of the percentages being 100 atomic percent.

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: Addition of Mo to a Zr--Mn--V--Cr--Co--Ni, a Zr--Mn--Cr--Co--Ni hydrogen storage alloy, or those including Ti as substitution for Zr improves high-rate discharge characteristics of the hydrogen storage alloy at low temperatures. The hydrogen storage alloy is of the general formula ZrMn.sub.a V.sub.b Mo.sub.c Cr.sub.d Co.sub.e Ni.sub.f, wherein 0.4.ltoreq.a.ltoreq.0.8, 0.ltoreq.b<0.3, 0<c.ltoreq.0.3, 0<d.ltoreq.0.3, 0<e.ltoreq.0.1, 1.0.ltoreq.f.ltoreq.1.5, 0.1.ltoreq.b+c.ltoreq.0.3, and 2.0.ltoreq.a+b+c+d+e+f.ltoreq.2.4, or Zr.sub.1-x Ti.sub.x Mn.sub.a V.sub.b Mo.sub.c Cr.sub.d Co.sub.e Ni.sub.f, wherein 0<x.ltoreq.0.5, 0.4.ltoreq.a.ltoreq.0.8, 0.ltoreq.b<0.3, 0<c.ltoreq.0.3, 0<d.ltoreq.0.3, 0<e.ltoreq.0.1, 1.0.ltoreq.f.ltoreq.1.5, 0.1.ltoreq.b+c.ltoreq.0.3, x.ltoreq.b+c+d+e, and 1.7.ltoreq.a+b+c+d+e+f.ltoreq.2.2 or Zr.sub.1- Ti.sub.x Mn.sub.a Mo.sub.c M.sub.y Cr.sub.d Ni.sub.f, wherein M is at least one selected from the group consisting of Fe, Cu, and Zn, and wherein 0<x.ltoreq.

Abstract: An alloy having improved resistance to hydriding as well as good corrosion resistance, adequate strength, fabricability and irradiation growth. These properties make the new alloy exceptionally suited for use in boiling water reactor components such as fuel channels, fuel cladding and fuel rod spacers. The class of alloys includes zirconium-based alloys having about 0.3-1.2% tin, about 0.8-1.4% chromium, about 0.05-0.7% iron, and the remainder substantially zirconium.

Abstract: A zirconium-based alloy with a reduced ahoy content is described that has resistance to both uniform and nodular corrosion comparable to present zirconium-based alloy compositions, such as Zircaloy-2. The alloy represents in essence a modified or diluted Zircaloy-2 or Zircaloy-4. The alloys of this invention are also expected to have improved uniform corrosion resistance at under high burn-up conditions The alloy comprises 0.05-0.09 weight percent of iron, 0.03-0.05 weight percent of chromium, 0.02-0.04 weight percent of nickel, 1.2-1.7 weight percent of tin and 0-0.15 weight percent oxygen, with a balance of zirconium. The iron chromium and nickel alloying elements form precipitates in the alloy matrix. The alloy is suitable for use as a cladding material for a fuel element housing fissionable nuclear materials in water cooled nuclear fission reactor.

Abstract: The method serves to manufacture tubes for constituting sheaths for nuclear fuel rods. A bar is made out of a zirconium-based alloy containing 50 ppm to 250 ppm iron, 0.8% to 1.3% by weight niobium, less than 1600 ppm oxygen, less than 200 ppm carbon, and less than 120 ppm silicon. The bar is heated to a temperature in the range 1000.degree. C. to 1200.degree. C. and is quenched in water. A blank is extruded after heating to a temperature in the range 600.degree. C. to 800.degree. C. and cold-rolled in at least four passes in order to obtain a tube, with intermediate heat treatment being performed between passes at temperatures in the range 560.degree. C. to 620.degree. C. A final heat treatment is performed at a temperature in the range 560.degree. C. to 620.degree. C., all of the heat treatments being performed under an inert atmosphere or a vacuum.

Abstract: A zirconium-based hydrogen storage alloys having the composition formula:Zr.sub.1-x Q.sub.x Cr.sub.1-Y-Z-A-B Mn.sub.Y Fe.sub.Z Co.sub.A V.sub.B Ni(I)wherein Q is Ti or Hf; 0<x.ltoreq.0.3; and 0<Y+Z+A+B<1, are disclosed. The Zr-based hydrogen storage alloy has a C-14 hexagonal structure and is mainly composed of single phase. The alloy is useable for a negative electrode material for secondary batteries. The Zr-based hydrogen storage alloy also has also a discharge capacity of 300.about.377 mAg/g and low reduction of discharge capacity at a low temperature and discharge rate.

Abstract: A composite wire microelectrode for making electro-chemical measurements, and method of making same. The microelectrode includes an inner conductive sensing wire and an outer tube that is oxidized to form a dielectric, self-healing oxide layer around the sensing wire.

Abstract: Disclosed are a hydrogen storage alloy which contains carbon in a proportion of from 30 to 500 ppm and is represented by the stoichiometric formula A.sub.x B.sub.5.0, wherein A is La or a mixture of La with at least one rare earth metal other than La, B is at least one metal selected from a group consisting of Al, Co, Cr, Cu, Fe, Mn, Ni, Ti, V, Zn and Zr, and x is a rational number in the range 0.95.ltoreq..times..ltoreq.1.00; and has a texture in which only the intermetallic compound phase named AB.sub.5 phase is present and every other intermetallic compound phase is absent: and a method of producing said alloy and an electrode using the same.

Abstract: A diamond-containing metal-matrix composite material is formed by dispersing pieces of diamond throughout a melt of a bulk-solidifying amorphous metal and solidifying the mixture. The mixture may then be remelted and resolidified at a rate sufficiently high that the metal matrix retains an amorphous structure upon cooling. The metal preferably has a composition of about that of a eutectic composition, and most preferably has a composition, in atomic percent, of from about 45 to about 67 percent total of zirconium plus titanium, from about 10 to about 35 percent beryllium, and from about 10 to about 98 percent total of copper plus nickel. The diamond is preferably low-grade or artificial diamond.

Abstract: Amorphous alloy comprising 30 to 75 atomic % Cr, the remainder being substantially at least one element selected from the group consisting of Ti and Zr and alloys represented by the general formula: X.sub.a Cr.sub.b M.sub.c wherein X is at least one element selected from the group consisting of Ti and Zr; M is at least one element selected from the group consisting of Mg, Al, Fe, Co, Ni, Cu, Mo and W; and a, b, and c are, in atomic percentage, a>20, 20 .ltoreq.b.ltoreq.75, 0<c .ltoreq.20 and a+b+c=100. The alloys are excellent in corrosion resistance and wear resistance, form a stable protective film and are spontaneously passive, even in corrosive environment such as a poorly oxidizing, highly corrosive HCl solution containing chlorine ions.

Abstract: An improved stainless steel composition and an improved stainless Ni-based alloy are disclosed for use in nuclear reactor environments. The improved stainless alloys include a stainless steel and a stainless nickel based alloy that are particularly well adapted for use in reactor components that are positioned adjacent to components formed from a zirconium based metal. The improved stainless steel is an austenitic stainless steel material that include less than approximately 0.2 percent manganese by weight, but does include sufficient austenitic stabilizer to prevent a martensitic transformation during fabrication or use in a reactor environment. In one preferred embodiment, the stainless alloy is formed without any significant amount of manganese.

Abstract: A fuel rod has a cladding including a thicker inner layer and a thin outer layer being metallurgically bound thereto. In view of the conditions prevailing on the inside of the cladding tube and the mechanical properties of the entire cladding tube, the inner layer is formed of zircaloy having a comparatively high Sn content and a low Fe and Fe+Cr content. The outer layer also contains virtually only zircaloy constituents, but in view of corrosion, H2 take-up and sensitivity to Li dissolved in the cooling water, the Fe and Fe+Cr content is greater than or at most equal to that of the inner layer, the chosen Sn content is less than 1.3% and the chosen Sn+Fe+Cr content is more than 1.0%. Low failure rates of the cladding tube are thereby achieved even for long service lives.

Abstract: An electrode (40) for a Ni/MHx storage cell (47) is prepared by providing a substrate (62) and providing an active material in a finely divided form. A paste (60) of a mixture of the active material, optionally a finely divided carbon powder, and a solution of a polymer in an organic solvent is formed. The paste (60) is coated onto the substrate (62). The paste-coated substrate (62) is immersed into water to wash away the organic solvent and to precipitate the polymer, completing the anode fabrication. This electrode (40) is assembled with another electrode (44) and as a separator (46) between the electrodes (40 and 44) and provided with an electrolyte (50), to form the electrochemical cell (47).

Abstract: A hydrogen storage alloy preferably used for electrodes in an alkaline storage battery is provided. The alloy is of the general formula ZrMn.sub.w V.sub.x Mo.sub.b M.sub.y Ni.sub.z, wherein M is at least one element selected from the group consisting of Fe and Co and 0.4.ltoreq.w.ltoreq.0.8, 0.ltoreq.x.ltoreq.0.3, 0.05.ltoreq.b.ltoreq.0.2, 0.ltoreq.y.ltoreq.0.2, 1.0.ltoreq.z.ltoreq.1.5, and 2.0.ltoreq.w+x+b+y+z.ltoreq.2.4. The alloy has C15-type Laves phases of a crystal structure similar to that of MgCu.sub.2 as a main alloy phase, and a lattice constant "a" such that 7.05 .ANG..ltoreq.a.ltoreq.7.13 .ANG..

Abstract: A hydrogen storage alloy electrode comprising a hydrogen storage alloy having a major phase of C15 (MgCu.sub.2) type Laves phase with a composition expressed as ZrMn.sub.w M.sub.x Cr.sub.y Ni.sub.z (where M is one or more elements selected from V and Mo), or its hydride. In this formula, one composition range is 0.6.ltoreq.w.ltoreq.0.8, 0.1.ltoreq.x.ltoreq.0.3, 0<y.ltoreq.0.2, and 1.2.ltoreq.z.ltoreq.1.5, and the other composition range is 0.6.ltoreq.w.ltoreq.0.8, 0.1.ltoreq.x.ltoreq.0.3, 0<y.ltoreq.0.2, and 0.8.ltoreq.z.ltoreq.1.2.

Abstract: A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.

Abstract: Alloys which form metallic glass upon cooling below the glass transition temperature at a rate appreciably less than 10.sup.6 K/s comprise beryllium in the range of from 2 to 47 atomic percent and at least one early transition metal in the range of from 30 to 75% and at least one late transition metal in the range of from 5 to 62%. A preferred group of metallic glass alloys has the formula (Zr.sub.1-x Ti.sub.x).sub.a (Cu.sub.1-y Ni.sub.y).sub.b Be.sub.c. Generally, a is in the range from 30 to 75% and the lower limit increases with increasing x. When x is in the range of from 0 to 0.15, b is in the range of from 5 to 62%, and c is in the range of from 6 to 47%. When x is in the range of from 0.15 to 0.4, b is in the range of from 5 to 62%, and c is in the range of from 2 to 47%. When x is in the range of from 0.4 to 0.6, b is in the range of from 5 to 62%, and c is in the range of from 2 to 47%. When x is in the range of from 0.6 to 0.

Abstract: The alloy of the present invention features controlled amounts of tin, nitrogen, and niobium and includes tin (Sn) in a range of greater than 0 to 1.50 wt. %, wherein 0.6 wt. % is typical. The alloy also has iron (Fe) in a range of greater than 0 to 0.24 wt. %, and typically 0.12 wt. %; chromium (Cr) in a range of greater than 0 to 0.15 wt. % and typically 0.10 wt. %; nitrogen (N) in a range of greater than 0 to 2300 ppm; silicon, in a range of greater than 0 up to 100 ppm, and typically 100 ppm; oxygen (O) in a range of greater than 0 and up to 1600 ppm, and typically 1200 ppm; niobium (Nb) in a range of greater than 0 wt. % to 0.5 wt. % and typically 0.45 wt. %; and the balance zirconium.

Abstract: A zirconium-based alloy for components in nuclear reactors with excellent resistance both to corrosion by water and water steam and to hydrogen absorption under operating conditions consists of 1.0-2.0 per cent by weight tin, 0.07-0.70 per cent by weight iron, 0.05-0.15 per cent by weight chromium, 0.16-0.40 per cent by weight nickel, 0,015-0.30, preferably 0,015-0.20 per cent by weight niobium, 0.002-0.05, preferably 0.015-0.05 per cent by weight silicon, 0.09-0.20, preferably 0.09-0.16 per cent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kinds than the above-mentioned substances.

Abstract: This active brazing preferably serves to braze (join) ((aluminum-)oxide-)ceramic parts or single crystals or metal parts or to braze (join) ((aluminum-)oxide-)ceramic parts to single crystals or ((aluminum-)oxide-)ceramic parts or single crystals to metal parts. In addition to the zirconium-nickel alloy, which is composed of 70 atom % to 85 atom % zirconium and 15 atom % to 30 atom % nickel, it contains titanium.

Abstract: A hafnium alloy consisting essentially of hafnium and containing Sn by 0.1-1.5 weight %, O by 0.03-0.2 weight %, Fe by 0.01-0.15 weight %, Zr by 0.02-2.0 weight %, and (1) Cr by 0.01-0.15 weight %, and Ni by less than 0.10 weight %, (2) Cr by 0.01-0.15 weight %, Ni by less than 0.10 weight %, and Mo by 0.01-0.2 weight %, (3) Nb by 0.2-1.0 weight %, or (4) Nb by 0.2-1.0 weight %, and Mo by 0.01-0.2 weight % has high neutron-absorbing capacity, high resistance to uniform and nodular corrosion, high tensile and creep strength, and good wear resistance, and is suited to be used as neutron absorber for nuclear power reactors.

Abstract: The specification describes novel zirconium-based hydrogen storage materials useful as negative electrodes for rechargeable batteries. The materials according to the present invention are represented by the following empirical formula:Zr-based metal hydrides+Mx (I)wherein M is a light rare earth metal selected from the group consisting of La, Nd, and Mm; 0<x<0.1; and the Zr-base metal hydrides means mainly that the metal hydrides are mainly in Zr-based Laves phase such as ZrCrNi, Zr (V.sub.0.33 Ni.sub.0.67).sub.2.4. Another group of the materials is represented by the following formula:ZrCr.sub.1+y Ni.sub.1+z (II)wherein, 0.ltoreq.y.ltoreq.0.2, and 0.ltoreq.z.ltoreq.0.2, provided that y and z cannot denote 0 concurrently. The negative electrodes made of these alloys need only a small number of activation cycles and thus, exhibit an improved activation behavior without any pretreatments for the activation.

Abstract: A structural part for a nuclear reactor fuel assembly includes a zirconium alloy material having at least one alloy ingredient selected from the group consisting of oxygen and silicon, a tin alloy ingredient, at least one alloy ingredient selected from the group consisting of iron, chromium and nickel, and a remainder of zirconium and unavoidable contaminants. The zirconium alloy material has a content of the oxygen in a range of substantially from 700 to 2000 ppm, a content of the silicon of substantially up to 150 ppm, a content of the iron in a range of substantially from 0.07 to 0.5% by weight, a content of the chromium in a range of substantially from 0.05 to 0.35% by weight, a content of the nickel of substantially up to 0.1% by weight, and a content of the tin in a range of substantially from 0.8 to 1.7% by weight.