Abstract: Method of manufacturing zirconium alloy tubular products containing (wt. %): niobium—0.9-1.7; iron—0.04-0.10; oxygen—0.03-0.10; silicon—less than 0.02, carbon—less than 0.02, and zirconium—as the base of the alloy. This includes an ingot melting by multiple vacuum arc remelting, mechanical processing of the ingot, heating, hot working of the ingot, subsequent mechanical processing for the production of tubular billets, heat treatment of the tubular billets, application of a protective coating and heating to a hot pressing temperature, hot pressing, removal of the protective coating, multi-stage cold radial forging, vacuum thermal treatment, multiple cold rolling runs with a total deformation degree of 50-80-% per run and a tubular coefficient of Q=1.0-2.7 with intermediate vacuum thermal treatment after each cold rolling operation, and final vacuum thermal treatment of the resulting tubular products carried out at the final size with subsequent final finishing operations.

Abstract: The fuel assembly includes at least one fuel rod and an outer channel with four sidewalls surrounding the fuel rod, the outer channel having a configuration based on a position of the fuel assembly within a core of the nuclear reactor, wherein at least a first select sidewall, of the four sidewalls of the outer channel, is a reinforced sidewall, the remaining sidewalls of the outer channel, other than the at least a first select sidewall, are non-reinforced sidewalls, the at least a first select sidewall being in a controlled location that faces and is directly adjacent to a control blade that is to be utilized in the nuclear reactor, wherein an entirety of the reinforced sidewall as a whole is at least one of thicker and made from a material that is more resistant to radiation-induced deformation as compared to an entirety of the non-reinforced sidewalls.

Abstract: A method for making a fuel rod cladding tube and a cladding tube are described. The method includes wrapping ceramic fibers, for example, SiC fibers in a SiC matrix, around a tube formed from a metal alloy, such as a zirconium alloy. The interstices of the SiC wrappings on the tube are at least partially filled with SiC nano-sized particles. The surface of the filled tube is exposed by atomic layer deposition, at temperatures ranging from 25° C. to 600° C., to at least one cycle of alternating, non-overlapping pulses of gaseous precursors containing carbon and silicon to form a SiC monolayer. The step of filling the interstices of the SiC wrappings on the tube with SiC nano-sized particles fills large voids in the SiC wrapping. The step of exposing the surface of the particle filled SiC windings to at least one cycle of gaseous pulses fills small voids in the SiC wrapping.

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: Described is a golf club with an outer surface comprising a low-friction ceramic material with suitable thickness and configuration. In one aspect, at least the striking surface and/or sole of a golf-club head is made of a low-friction material including at least one of: titanium nitride, titanium carbonitride, titanium oxynitride, titanium carbide, titanium aluminum nitride, aluminum titanium nitride, titanium silicon nitride, titanium niobium nitride, titanium zirconium nitride, silicon nitride, aluminum oxide, zirconium oxide, silicon oxide, zirconium nitride, chromium nitride, chromium carbonitride, chromium aluminum nitride, aluminum chromium nitride, titanium aluminum silicon nitride, and one or more combinations thereof.

Abstract: Described are articles having, at least, an outer surface comprising unalloyed oxidized Zirconium with Niobium having a thickness and configurations suitable for sports equipment, golf clubs, aircraft, boat hulls, motor vehicle, propellers, helicopter rotors, and various other non-medical applications.

Abstract: Described are articles having, at least, an outer surface comprising unalloyed oxidized Zirconium with Niobium having a thickness and configurations suitable for sports equipment, golf clubs, aircraft, boat hulls, motor vehicle, propellers, helicopter rotors, and various other non-medical applications.

Abstract: A treatment of a heater tube intended to be used in a pressurizer of the primary cooling system of a nuclear reactor. In particular, the heater tube comprises a heater housed in a substantially cylindrical sheath. The material of which this sheath is made is a work-hardened austenitic stainless steel. In particular, the external surface of the sheath is liable to undergo a stress corrosion during use of the heatertube. The method includes a heat treatment step, preferably using induction heating, in which the external surface of the sheath is heat-treated so as to recrystallize the material of the sheath at least on the surface thereof.

Abstract: Methods of preparing a surface of a cast zirconium alloy substrate for oxidation, the method including hot isostatic pressing a cast substrate of near shape dimensions, heating the cast substrate, machining the cast substrate to desired shape dimensions, and treating the surface of the cast substrate to accept an oxide layer. in some examples, treating the surface of the cast substrate may include polishing the surface, peening the polished surface, and finishing the peened surface. Additional or alternative examples may include heat treating a cast substrate of near shape dimensions to define a homogenized grain structure within the cast substrate, machining the heat treated cast substrate to desired shape dimensions, and surface treating the machined cast substrate to modify its structure to define a recrystallized modified grain structure defining a reduced grain boundary size.

Abstract: Methods for producing alloy strips that demonstrate improved formability are disclosed. The strips have a crystalline microstructure suitable for improved formability in the manufacture of various articles such as panels for plate heat exchangers and high performance tower packing components.

Abstract: Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.

Abstract: Formed alloy strips including zirconium alloy strips that demonstrate improved formability are disclosed. The strips of the present disclosure have a purity and crystalline microstructure suitable for improved formability, for example, in the manufacture of certain articles such as panels for plate exchangers and high performance tower packing components.

Abstract: Methods of making surface hardened medical implants comprising providing a biocompatible alloy with a surface comprising an oxide or nitride layer, diffusing at least a portion of the respective oxygen or nitrogen from the oxide or nitride layer the substrate for a period of time to form a diffusion hardened zone of desired thickness. The period of time is based at least on (1) the diffusivity of a diffusing specie in the oxide or nitride layer, (2) a desired hardness profile of at least a portion of said implant defined by a function selected from the group consisting of: an error function, an exponential function, a near uniform distribution function, and any sequential combination thereof, or (3) a desired thickness of said oxide or nitride layer to be retained.

Abstract: Methods of refining the grain size of titanium and titanium alloys include thermally managed high strain rate multi-axis forging. A high strain rate adiabatically heats an internal region of the workpiece during forging, and a thermal management system is used to heat an external surface region to the workpiece forging temperature, while the internal region is allowed to cool to the workpiece forging temperature. A further method includes multiple upset and draw forging titanium or a titanium alloy using a strain rate less than is used in conventional open die forging of titanium and titanium alloys. Incremental workpiece rotation and draw forging causes severe plastic deformation and grain refinement in the titanium or titanium alloy forging.

Abstract: A method of producing a seamless, tubular product includes centrifugally casting a corrosion resistant alloy into a tubular workpiece having an inner diameter and an outer diameter. The method then removes material from the inner diameter of the workpiece and subjects the workpiece to at least about a 25% wall reduction at a temperature below a recrystallization temperature of the workpiece using a metal forming process. The metal forming process includes radial forging, rolling, pilgering, and/or flowforming.

Abstract: In light of the recent analytical technology demanded of fast and accurate measurement of high purity materials, a zirconium crucible is provided for melting an analytical sample and is capable of inhibiting the inclusion of impurities from the crucible by using a high-purity crucible, improving the durability of high-purity zirconium as an expensive crucible material, and increasing the number of times that the zirconium crucible can be used. With this zirconium crucible used for melting an analytical sample in the pretreatment of the analytical sample, the purity excluding gas components is 3N or higher, and the content of carbon as a gas component is 100 mass ppm or less.

Abstract: A method of manufacturing an optimized sheet metal (1) of a zirconium based alloy is described, which optimized sheet metal (1) defines a sheet plane (BA). The method comprises the steps of providing a sheet metal (2) of a zirconium based. alloy, subjecting the sheet metal (2) to at least a preparing cold rolling and a final cold rolling, wherein the preparing cold rolling and the final cold rolling are both performed in a common rolling direction, and heat treating the sheet metal (1) between the preparing cold rolling and the final cold rolling so that the zirconium based alloy is partially re-crystallized. A method of manufacturing a spacer grid using an optimized sheet metal (1) according to the invention is also described.

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: Method, and articles therefrom, for providing a hard, abrasion-resistant, attractive, oxide surface layer of selectable thickness and having an outer appearance within the scale from gray to black, to a zirconium titanium alloy article by heating the article in an oxygen containing atmosphere.

Abstract: Method, and articles therefrom, for providing a hard, abrasion-resistant, attractive, oxide surface layer of selectable thickness and having an outer appearance within the scale from gray to blackness, to a zirconium titanium alloy article by heating the article in an oxygen containing atmosphere.

Abstract: The invention concerns a method of producing and treating a sheet suited to be used as a component or as a part of a component in a fuel assembly for a nuclear light water reactor, which method comprises: a) producing a sheet of a Zr-based alloy by forging, hot rolling and cold rolling in a suitable number of steps, b) carrying out an ?+? quenching or a ? quenching of the sheet when the sheet has been produced to a thickness which is equal to or almost equal to the final thickness of the finished sheet, c) heat treating the sheet in the ?-phase temperature range of said alloy, wherein the sheet is stretched during the heat treatment according to step c). The invention also concerns a use of a sheet that is produced and treated according to this method, and to methods and fuel assemblies of which said sheet forms a part.

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

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

Abstract: The present disclosure provides methods of making an improved composition and medical implant made therefrom. The methods generally comprise forming a ceramic layer, diffusion hardening, and optionally, forming another ceramic layer. The present disclosure provides methods of making an improved composition having a thick diffusion hardened zone and orthopedic implants comprising the improved composition.

Abstract: The invention relates to a method of producing a flat zirconium alloy product with a Kearns factor (cross direction) of between 0.3 and 0.7. The inventive method consists in: producing an ingot containing Nb=0.5 to 3.5%, Sn=0 to 1.5%, Fe=0 to 0.5%, Cr+V=0 to 0.3%, S=0 to 100 ppm, O=0 to 2000 ppm, Si=0 to 150 ppm, the remainder being zirconium and impurities; shaping the aforementioned ingot; performing one or more hot rolling operations in order to obtain a flat product, whereby the last operation is performed at between(810?20×Nb %)° C. and 1100° C. and is not followed by any quenching from phase ?+? or ?; optionally performing an annealing operation at a maximum of 800° C.; and performing one or more cold rolling and annealing operations, said annealing operations being performed at a maximum of 800° C. The invention also relates to the flat zirconium alloy product thus obtained.

Abstract: Methods of refining the grain size of titanium and titanium alloys include thermally managed high strain rate multi-axis forging. A high strain rate adiabatically heats an internal region of the workpiece during forging, and a thermal management system is used to heat an external surface region to the workpiece forging temperature, while the internal region is allowed to cool to the workpiece forging temperature. A further method includes multiple upset and draw forging titanium or a titanium alloy using a strain rate less than is used in conventional open die forging of titanium and titanium alloys. Incremental workpiece rotation and draw forging causes severe plastic deformation and grain refinement in the titanium or titanium alloy forging.

Abstract: A method for manufacturing a sheet metal for use in a boiling water nuclear reactor and such a sheet metal. The method includes providing a material of a zirconium alloy that includes zirconium, and whose main alloying materials include niobium. The material is annealed so that essentially all niobium containing secondary phase particles are transformed to ?-niobium particles.

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: 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: Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage ?+? or ?-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10?19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

Abstract: A method of manufacturing an optimized sheet metal (1) of a zirconium based alloy is described, which optimized sheet metal (1) defines a sheet plane (BA). The method comprises the steps of providing a sheet metal (2) of a zirconium based. alloy, subjecting the sheet metal (2) to at least a preparing cold rolling and a final cold rolling, wherein the preparing cold rolling and the final cold rolling are both performed in a common rolling direction, and heat treating the sheet metal (1) between the preparing cold rolling and the final cold rolling so that the zirconium based alloy is partially re-crystallized. A method of manufacturing a spacer grid using an optimized sheet metal (1) according to the invention is also described.

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

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

Abstract: A method of forming bulk metallic glass engineering materials, and more particularly a method for forming coarsening microstructures within said engineering materials is provided. Specifically, the method forms ‘designed composites’ by introducing ‘soft’ elastic/plastic inhomogeneities in a metallic glass matrix to initiate local shear banding around the inhomogeneity, and matching of microstructural length scales (for example, L and S) to the characteristic length scale RP (for plastic shielding of an opening crack tip) to limit shear band extension, suppress shear band opening, and avoid crack development.

Abstract: A process of manufacturing zirconium alloy. The process may be used to make a nuclear fuel guide tube and/or a measuring tube which are main components of a nuclear fuel assembly structure. While a nuclear fuel guide tube and a measuring tube are manufactured by performing three-step cold working, and intermediate and final thermal annealing from a semi-finished TREX shell in the conventional method, the present invention relates to zirconium alloy undergoing two-step cold working, and intermediate and final thermal annealing from a TREX shell, resulting in enhanced strength and corrosion resistance.

Abstract: A large ingot is produced by casting the zirconium alloy, then the ingot is forged in two stages to obtain the semi-finished product wherein the first stage of forging the ingot is performed at a temperature at which the zirconium alloy is in a state comprising crystalline ? and ? phases.

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

Abstract: The invention concerns a method of producing a cladding tube for nuclear fuel for a nuclear boiling water reactor. According to the method, a tube is formed which comprises an outer cylindrical component (10) mainly containing zirconium and an inner cylindrical component (20) metallurgically bonded to the outer component (10), wherein also the inner component (20) at least mainly contains zirconium. The inner component (20) has a lower recrystallization temperature than the outer component (10). The cladding tube is final annealed at a temperature and during a time such that the inner component (20) substantially completely recrystallizes and such that the outer component (10) partly recrystallizes but to a lower extent than the inner component (20). The invention also concerns a cladding tube, a fuel assembly for a boiling water reactor as well as the use of a cladding tube.

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

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

Abstract: A fuel channel according to example embodiments for a nuclear reactor may have an elongated and hollow body with a multi-layer structure. The multi-layer structure may include a core layer and at least one cladding layer metallurgically-bonded to the core layer. The core layer and the at least one cladding layer may be alloys having different compositions. For instance, the core layer may be significantly more resistant to irradiation growth and/or irradiation creep than the at least one cladding layer, and the at least one cladding layer may have an increased resistance to hydrogen absorption and/or corrosion relative to the core layer. Accordingly, the distortion of the fuel channel may be reduced or prevented, thus reducing or preventing the interference with the movement of the control blade.

Abstract: A method for manufacturing a sheet metal for use in a boiling water nuclear reactor and such a sheet metal. The method includes providing a material of a zirconium alloy that includes zirconium, and whose main alloying materials include niobium. The material is annealed so that essentially all niobium containing secondary phase particles are transformed to ?-niobium particles.

Abstract: A method of producing a cladding tube for nuclear fuel for a nuclear pressure water reactor includes forming a tube which at least principally consists of a cylindrical tube component of a zirconium-based alloy, where the alloying element, except for zirconium, which has the highest content in the alloy is niobium, wherein the niobium content in weight percent is between about 0.5 and about 2.4 and wherein no alloying element, except for zirconium and niobum, in the alloy, has a content which exceeds about 0.2 weight percent. The cladding tube is then annealed such that the tube component is partly but not completely recrystallized. The degree of recrystallization in the tube component is higher than about 40% and lower than about 95%. A fuel assembly for a nuclear pressure water reactor also has a plurality of such cladding tubes.

Abstract: A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.

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

Abstract: The present invention relates to a new composition and medical implant made therefrom, the composition comprising a thick diffusion hardened zone, and preferably further comprising a ceramic layer. The present invention relates to orthopedic implants comprising the new composition, methods of making the new composition, and methods of making orthopedic implants comprising the new composition.

Abstract: An article of titanium or a titanium-based alloy, or of zirconium or a zirconium-based alloy is case hardened by heat treatment for at least 12 hours at one or more temperatures in the range of 850° C. to 900° C. and at a pressure in the order of atmospheric pressure in an oxygen diffusion atmosphere. The oxygen diffusion atmosphere comprises a carrier gas such as argon which does not react chemically with the article the said temperature range and molecular oxygen. The concentration of oxygen as the oxygen diffusion atmosphere is in the range of 10 volumes per million to 400 volumes per million.

Abstract: One object of the present invention is to provide a production method for a nuclear fuel assembly support grid that improves the corrosion resistance of welded parts without impairing the characteristics of the support grid so as to be able adequately withstand highly efficient operation. In order to achieve the object, the present invention provide a production method for a nuclear fuel assembly support grid comprising the steps of: assembling a plurality of straps in a grid form; welding intersections of each strap; and carrying out annealing thereafter to precipitate an intermetallic compound on the welded parts.

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.