Abstract: In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.

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: 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: In a method of fabricating a channel box for use in a nuclear reactor, Zr-alloy sheet material is formed into a tubular channel box. The method includes solution heat treatment of the Zr-alloy sheet material including quenching from a temperature at which .beta.-phase is present. After the solution heat treatment, portions of the Zr-alloy sheet are thinned relative to other portions by a non-stressing thinning process, such as chemical etching in a bath. The corrosion resistance imparted by heat treatment is retained, and the heat treatment itself is easily performed on material of uniform thickness.

Abstract: A method of manufacturing components made of zirconium-based alloy by combining heat treatment with thermal sizing. The heat treatment includes heating the component to a temperature which initiates the transformation from a hexagonal close-packed crystallographic phase of uniform texture to a body-centered cubic crystallographic phase and then quenching to a quench temperature at a rate which initiates transformation to a hexagonal close-packed crystallographic phase having a texture factor f.sub.L =0.28-0.38. The thermal sizing includes heating the component to a temperature less than the quench temperature, but sufficient to anneal the component, and then cooling. Preferably, the thermal sizing is performed twice: before and after the heat treatment.

Abstract: A process for producing an amorphous alloy material characterized by imparting ductility to an amorphous alloy having a supercooled liquid region by giving a prescribed amount of strain at a prescribed strain rate to the alloy in the glass transition temperature region of the alloy. The amorphous alloy may be in the form of spherical or irregular-shaped powders or thin ribbons or in the form of primary consolidated shapes thereof or an amorphous alloy casting. The amount of strain and strain rate are preferably 50% or greater and 2.times.10.sup.-2 /sec or higher, respectively, and the worked amorphous alloy material is preferably allowed to cool in a furnace or spontaneously. Suitable examples of the amorphous alloy to be employed include Al-TM-Ln, Mg-TM-Ln, Zr-TM-Al and Hf-TM-Al alloys, wherein TM is a transition metal element and Ln is a rare earth metal element. The thus obtained amorphous alloy is greatly improved in the prevention of embrittlement in hot working peculiar to the alloy.

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.

Abstract: A composite nuclear fuel container for service in water cooled nuclear fission reactor plants having improved resistance to corrosion, and a method of producing same. The invention comprises each component of the fuel container being of specific compositions which have been heat treated to transform their microcrystalline structure in such a manner to optimize the corrosion resistance of each component of the fuel container.

Abstract: A Zirlo alloy formed by beta quenching, hot deforming, recrystallize annealing and then cold deforming said alloy a plurality of times with recrystallize anneal steps performed between the cold deforming steps followed by stress relief annealing. The fabricating method can include a late stage beta quench step in place of one of the recrystallize anneal steps.

Abstract: Zircaloy 2 or 4 strip is heat treated in the beta range, followed by rapid cooling by passing the strip between a first and second roller pair, each roller pair having two oppositely disposed rollers gripping the strip. Each roller pair is connected to a source of an electric current so as to complete an electric circuit including the source, the roller pairs and the strip, which causes heating of the strip to the beta range. The strip is heated at a rate less than 40.degree. C./sec between 750.degree. and 1000.degree. C., held at 1000.degree.-1100.degree. for less than 2 minutes and cooled at a rate of at least 40.degree. C./sec between 1000.degree. C. and 600.degree. C.

Abstract: A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing tin in a range of 0.45 to 0.75 wt. %, and typically 0.6 wt. %; iron in a range of 0.4 to 0.53 wt. %, and typically 0.45 percent; chromium in a range of 0.2 to 0.3 wt. %, and typically 0.25 percent; niobium in a range of 0.3 to 0.5 wt. %, and typically 0.45 wt. %; nickel in a range of 0.012 to 0.03 wt. %, and typically 0.02 wt. %; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 1,000 to 2,000 ppm, and typically 1,600 ppm, with the balance zirconium. The addition of iron and niobium improves mechanical properties of the alloy with its lower level of tin, while corrosion resistance is addressed by having an iron level of 0.45 wt. % and an iron/chromium ratio on the order of 1.5. The addition of niobium also counters the effect of higher iron on the hydrogen absorption characteristics of the alloy.

Abstract: This is an improved method of fabricating Zircaloy-4 strip. The method is of the type wherein Zircaloy-4 material is vacuum melted, forged, hot reduced, beta-annealed, quenched, hot rolled, subjected to a post-hot-roll anneal and then reduced by at least two cold rolling steps, including a final cold rolling to final size, with intermediate annealing between the cold rolling steps and with a final anneal after the last cold rolling step. The improvement comprises: (a) utilizing a maximum processing temperature of 620.degree. C. between the quenching and the final cold rolling to final size; (b) utilizing a maximum intermediate annealing temperature of 520.degree. C.; and (c) utilizing hot rolling, post-hot-roll annealing, intermediate annealing and final annealing time-temperature combinations to give an A parameter of between 4.times.10.sup.-19 and 7.times.10.sup.

Abstract: A method for improving the corrosion resistance of a zirconium-based material in an acid environment. A laser beam is scanned across the entire surface of the material to cause surface melting of the material. A rapid self-quenching is provided by the underlying substrate. Homogeneous material formed during solidification of the molten pool improves the corrosion resistance. Alloy enriched diffuse regions, i.e., tin and iron, develop parallel to each other and the periphery of the edge of the melt pool. In this manner, the laser surface melting removes the intermetalics by dissolving the precipitates, thus removing the source of localized corrosion. This greatly reduces the capability of the iron to act anodically to cause the zirconium to ionize, disassociate from the matrix, and migrate into the acid solution.

Abstract: This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200.degree.-1300.degree. F., and to a beta quench two steps prior to final size.

Abstract: A method of making a strip of ZIRCALOY 2 or 4 is disclosed wherein an ingot is worked, roughly shaped into a billet then quenched from the beta range, hot rolled in alpha range, annealed and cold rolled to 0.3 to 0.9 mm. The O and C, in ppm, are selected to satisfy the formula: O.sub.2 <1200-0.75 x C (R) so that a T texture is obtained systematically for thicknesses of at least 0.8 mm. The disclosure also concerns the strips obtained. The method can be applied to obtaining strips of excellent formability for the production of components for nuclear water reactors.

Abstract: An improved procedure for producing composite constructed nuclear fuel containers for service in water cooled nuclear fission reactors is disclosed. The improved production procedure maximizes the advantageous characteristics of the respective components of the composite unit. The procedure of the invention comprises heat treating the two components of a tube stock and liner stock separately prior to their assembly.

Abstract: A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance under neutron irradiation environment in a zirconium alloy containing tin in a range of 0.8 to 1.2 percent; iron in a range of 0.2 to 0.5 percent, and typically 0.35 percent; chromium in a range of 0.1 to 0.4 percent, and typically 0.25 percent; niobium in a range of from a measurable amount up to 0.6 percent, and typically 0.30 percent; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 900 to 1800 ppm, typically 1600 ppm. The silicon is added as an alloying element to reduce hydrogen absorption by the alloy and to reduce variations in the corrosion resistance with variations in the processing history of the alloy.

Abstract: A method for annealing a Zircaloy member having a cold worked or beta quenched crystal structure to mitigate the reduction in nodular corrosion resistance caused by the anneal comprises, annealing the member in an atmosphere comprising oxygen and the balance an inert atmosphere to form an adherent black oxide on the member.

Abstract: A method of hardening the surface of titanium and its alloys, and other structural metals which form hard carbides, by treating the surface thereof with a moving, discontinuous carbon arc.The metal surface to be hardened, and a carbon electrode are made opposite poles of an electric current source, and moved and/or rotated with respect to each other so that a multiplicity of discontinuous electric arcs are produced between the carbon electrode and the metal surface.Carbon particles transfer through the arc and alloy within craters of the instantly liquified and chilled substrate, producing a surface layer which, in the case of titanium, is hard and tough and adherent enough to form the working surface of abrasive cutting tools.The process improves the appearance and durability of consumer items and reduces friction and wear on machine parts.

Abstract: This invention is for the processing of a somewhat broader range of compositions, including ZIRLO material. It controls creep rate in an alloy having, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.28 of at least one of iron, nickel and chromium and up to 220 ppm carbon, and the balance essentially zirconium. The method is of a type which utilizes subjecting the material to a post extrusion anneal, a series of intermediate area reductions and intermediate recrystallization anneals, with one of the intermediate recrystallization anneals possibly being a late stage beta-quench, a final pass area reduction, and a final stress relief anneal.

Abstract: This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200.degree.-1300.degree. F., and to a beta quench two steps prior to final size.