Showing papers on "Zirconium alloy published in 1975"
TL;DR: In this paper, the dynamic elastic moduli of Zircaloy-2, Zr-1.15 wt% Ci-0.1 wt % Fe and Zr 2.5wt% Nb have been determined over the temperature range 293-773 K.
101 citations
TL;DR: In this article, the average size of the hydrides, the proportion of hydride located at grain boundaries, and proportion of the equilibrium δ-hydride increased as the hydrogen concentration was increased and/or the rate of cooling was decreased.
75 citations
60 citations
21 Mar 1975
46 citations
TL;DR: In this article, a model for the oxidation of zirconium alloys was proposed, where metal electrodes were evaporated on to the oxide films and the dc conduction of the alloy-oxide-metal diodes was investigated.
38 citations
TL;DR: In this paper, the authors discussed in view of life-limiting aspects; under normal operating conditions of a PWR, the external corrosion is not life limiting and localized oxide lenses (nodular corrosion) have been observed.
35 citations
Patent•
13 Feb 1975
TL;DR: The low pressure braze bonding of members comprised of, for example, titanium and zirconium alloys is accomplished with the use of foil-type braze alloy preforms as discussed by the authors.
Abstract: The low pressure braze bonding of members comprised of, for example, titanium and zirconium alloys is accomplished with the use of foil-type braze alloy preforms. The braze alloy preforms comprise a titanium-zirconium foil which has been coated on at least one side with a layer of nickel which functions as a eutectic depressant alloying agent. Upon heating, at a temperature below the beta transus of titanium, a liquid phase will form and the nickel will partially alloy with and migrate into the foil and workpieces and solidification of the resulting joint may thereafter be obtained.
30 citations
TL;DR: In this paper, the thermal conductivity and heat capacity of Zircaloy-2, −4 and Unalloyed Zirconium were investigated and shown to have high thermal capacity.
Abstract: (1975). Thermal Conductivity and Heat Capacity of Zircaloy-2, −4 and Unalloyed Zirconium. Journal of Nuclear Science and Technology: Vol. 12, No. 10, pp. 661-662.
29 citations
TL;DR: In this article, a new method for the chemical vapor deposition of ZrC and C-ZrC alloys has been developed for the fabrication of coated particle nuclear fuels of the type used in the large High Temperature Gas-Cooled Reactor.
26 citations
Patent•
19 May 1975TL;DR: In this article, a zirconium base niobium alloy is produced, having improved ductility after irradiation with fast neutrons, by heating in a protective atmosphere, and water quenching the ZIRCONIUM base alloy to produce a fine martensitic structure supersaturated with the or each alloying element.
Abstract: A zirconium base alloy is produced, having improved ductility after irradiation with fast neutrons, by heating in a protective atmosphere a zirconium base alloy containing precipitates in the form of at least one alloying element (e.g. Nb, Mo, Ni or Cr), which is soluble with the zirconium in the β phase and insoluble therewith in the α phase, until the precipitates have dissolved, water quenching the zirconium base alloy to produce a fine martensitic structure supersaturated with the or each alloying element, working the zirconium base alloy in steps reducing the cross-sectional area 10% to 20% of the original cross-section, with annealing below recrystallization temperature for at least 10 minutes in the α phase between steps, until a total reduction of 70%-75% of the original cross-section is achieved, and then annealing the zirconium base alloy so that simultaneous recrystallization and precipitation of the or each alloying element occurs. An alloy is produced having an average grain diameter of 0.1-0.5 microns which is particularly useful for nuclear fuel sheathing. An example of the procedure for a zirconium base niobium alloy is given.
24 citations
Patent•
06 Oct 1975
TL;DR: The inclusion of small interrelated amounts of zirconium and columbium to ferritic stainless steels results in a stabilized steel having good pitting corrosion resistance and good ductility as mentioned in this paper.
Abstract: The inclusion of small interrelated amounts of zirconium and columbium to ferritic stainless steels results in a stabilized steel having good pitting corrosion resistance and good ductility.
TL;DR: In this article, an investigation was made into the occurrence of a strength differential in the Zircaloy cladding of LWR fuels, and into the effect such strength differential can have on the analytical predictions of cladding creep collapse during fuel densification.
TL;DR: In this paper, an experimental study was made of the effects of deformation on the oxidation of Zircaloy-2 reactor fuel cladding in flowing steam in the temperature range 700 to 1300°C.
01 Mar 1975
Patent•
26 Jun 1975TL;DR: In this article, Zirconium-base alloy channels, fuel cladding tubes and other components are made resistant to accelerated pustular corrosion in a boiling water reactor environment by coating them with a small amount of a suitable electronically conducting material.
Abstract: Zirconium-base alloy channels, fuel cladding tubes and other components are made resistant to accelerated pustular corrosion in a boiling water reactor environment by coating them with a small amount of a suitable electronically conducting material.
TL;DR: In this article, the effects of alloy additions of zirconium, hafnium, molybdenum, tungsten, rhenium, ruthenium and iridium on the hardness of binary and ternary niobium alloys were determined.
Abstract: The effects of alloy additions of zirconium, hafnium, molybdenum, tungsten, rhenium, ruthenium, osmium, rhodium, and iridium on the hardness of niobium was determined. Both binary and ternary alloys were investigated by means of hardness tests at 77 K and 300 K. Results showed that atomic size misfit plays a dominant role in controlling hardness of binary niobium alloys. Alloy softening, which occurred at dilute solute additions, is most likely due to an extrinsic mechanism involving interaction between solute elements and interstitial impurities.
TL;DR: In this paper, the electrical resistivity of samples of niobium and 75% Nb 25% Zr alloy have been measured between the superconducting critical temperatures and room temperature.
Abstract: The electrical resistivity of samples of niobium and 75% Nb 25% Zr alloy have been measured between the superconducting critical temperatures and room temperature. The temperature dependent component of the resistivity has been compared with phenological equations, and it is shown that phonon induced transitions between s and d bands are largely responsible for the observed resistivity. The effect of finite fluctuations of the superconducting order parameter is discussed.
01 Mar 1975-Journal of Research of the National Bureau of Standards Section A: Physics and Chemistry
TL;DR: Simultaneous measurements of specific heat, electrical resistivity and hemispherical total emittance of hafnium containing 3.12 weight percent zirconium in the temperature range 1500 to 2400 K by a subsecond duration, pulse heating technique are described.
Abstract: Simultaneous measurements of specific heat, electrical resistivity and hemispherical total emittance of hafnium containing 3.12 weight percent zirconium in the temperature range 1500 to 2400 K by a subsecond duration, pulse heating technique are described. The measurements indicate decreases in specific heat (by about 13%) and in electrical resistivity (by about 8%) as the result of the α → β transformation. Estimated inaccuracies of the measured properties are: 3 percent for specific heat, 1 percent for electrical resistivity and 5 percent for hemispherical total emittance.
01 Jan 1975
01 Jun 1975
TL;DR: In this article, high-temperature oxidation of silicon-base materials was investigated and its properties and microstructures of high- temperature Ti-base alloys were analyzed using an electron microprobe.
Abstract: : ;Contents: High-temperature oxidation of silicon-base materials; High-temperature corrosion of experimental Ni-Cr-Al alloys; Transport properties of high-temperature oxides; Mechanical properties and microstructures of high- temperature Ti-base alloys; Electron-microprobe analysis of high-temperature materials.
TL;DR: In this article, the ductile-brittle transition temperature of tungsten and W−C alloys with zireonium, niobium, and tantalum was investigated.
Abstract: 1.
Alloying of tungsten and W−C alloys with zireonium, niobium, and tantalum increases the short-term and also the long-term strength. The strength is increased most by small additions of the alloying element (up to 0.1 at. %). In effectiveness of hardening at temperatures ≤0.6Tm the elements investigated are arranged in the following order: Zr, Nb, Ta.
2.
At temperatures ≥0.6Tm separate and combined alloying of tungsten with carbon and substitutional elements of groups IV and V does not improve the heat resistance.
3.
Alloying elements raise the ductile-brittle transition temperature Tx of tungsten and W−C alloys. The increase of Tx is highest with the addition of zirconium.
TL;DR: In this article, the mechanism of heterogeneous internal hydriding, the effect of bore surface condition, the critical amount of hydrogen and criteria by which it may be specified are discussed.
TL;DR: In this article, a thermal diffusion experiment was performed with zircaloy-2 fuel cladding tubes containing hydrogen beyond the terminal solid solubility, and a modified diffusion model was presented to explain the experimental results.
Abstract: The thermal diffusion of hydrogen is one of causes of uneven hydride precipitation in zircaloy fuel cladding tubes that are used in water reactors. In the diffusion model of hydrogen in zircaloy, the effects of the hydride on the diffusibility of hydrogen has been regarded as negligibly small in comparison with that of hydrogen dissolved in the matrix. Contrary to the indications given by this model, phenomena are often encountered that cannot be explained unless hydride platelets have considerable ostensible diffusibility in zircaloy. In order to determine quantitatively the diffusion characteristics of hydrogen in zircaloy, a thermal diffusion experiment was performed with zircaloy-2 fuel cladding tubes containing hydrogen beyond the terminal solid solubility. In this experiment, a temperature difference of 20°–30°C was applied between the inside and outside surfaces of the specimen in a thermal simulator. To explain the experimental results, a modified diffusion model is presented, in which the effects...
Patent•
25 Sep 1975
TL;DR: An additive and method of making zirconium additions to steel is provided in this article in which an alloy of about 70% to 90% zirconsium and the balance iron with residual impurities is formed into uniform sized pieces and added to a bath of molten steel with various possible techniques.
Abstract: An additive and method of making zirconium additions to steel is provided in which an alloy of about 70% to 90% zirconium and the balance iron with residual impurities is formed into uniform sized pieces and added to a bath of molten steel with various possible techniques.
TL;DR: For annealed zirconium alloys, the damping was critically prestrain dependent as mentioned in this paper and the peak height increased with increasing number of cycles at a strain amplitude of 3.0 × 10−4.