Showing papers on "Zirconium alloy published in 1983"
TL;DR: In this article, the formation of macroscopic hydride stacks is investigated and the role of the texture of the alloy and of a stress acting on the basal planes in determining the orientation of the stacks is explained.
168 citations
TL;DR: In this article, the role played by the H2 gas in the formation of nodular corrosion in Zircaloys has been clarified, and the second phase particles of the ZrO2-Zircaloy have been identified.
65 citations
TL;DR: In this paper, the same authors compared the properties of glassy and crystal-line alloys and showed that inhomogeneity, caused by precipitation of a second phase, did not alter the corrosion behavior from that of single phase Cu60Zr40.
Abstract: Differences in structure between crystalline and glassy copper-zirconium alloys lead to subtle increases in the corrosion rate of crystalline compared to glassy material. Glassy alloys of Cu60Zr40 were melt spun and subsequently devitrified, yielding single phase polycrystalline material. Comparing the potentiodynamic polarization response of these structural types revealed no significant difference in ϕcorr. ba, bc, icorr. and io. Other alloys, Cu58Zr42 and Cu55Zr45, compared in glassy and crystal-line forms revealed that inhomogeneity, caused by precipitation of a second phase, did not alter the corrosion behavior from that of single phase Cu60Zr40. Corroded glassy surfaces were generally smooth except for scattered hemispherical features, while crystalline surfaces were densely populated with these features. Corrosion of copper-zirconium alloy occurs by the selective dissolution of zirconium in the vicinity of ϕcorr, whereas, at potentials noble to −0.1 VSCE, copper contributes to the anodic c...
47 citations
46 citations
TL;DR: In this article, integral tests of rod-burst, oxidation and thermal-shock were performed using simulated fuel containing A1203 pellets sheathed in Zircaloy-4 specimen cladding, filled with He gas, and sealed.
Abstract: With a view to examining the failure-bearing capability of Zircaloy-4 cladding under postulated Loss-of-Coolant Accident condition in LWRs, integral tests of rod-burst, oxidation and thermal-shock were performed using simulated fuel containing A1203 pellets sheathed in Zircaloy-4 specimen cladding, filled with He gas, and sealed. This simulated fuel rod was oxidized in steam flowing at the isothermal oxidation temperatures between 920 and 1,330°C for duration ranging of 3~180 min after the cladding burst. After isothermal oxidation, the rod was quenched with bottom-flooding water under the condition of constraint or no constraint. The failure boundary oxidation condition of the cladding on quenching under no constraint condition lay in the region of 35~38% ECR for the isothermal oxidation temperatures between 1,050 and 1,330°C. For the temperatures ranging 970~1,050°C, the boundary value of ECR was somewhat lower than that obtained for higher temperatures. The failure boundary oxidation condition of the c...
42 citations
Patent•
28 Sep 1983
TL;DR: In this paper, a method and apparatus for measuring a liner thickness of a zirconium liner provided at the inner surface of a ZIRconium alloy tube, the principle of measurement of which is to insert coils into the tube to generate an eddy current, detect the impedance component in the direction perpendicular to the direction of coil impedance change caused by the lift-off variation between the coils and the inner surfaces of tube, and obtain the liner thickness on the basis of impedance component.
Abstract: A method and apparatus for measuring a liner thickness of a zirconium liner provided at the inner surface of a zirconium alloy tube, the principle of measurement of which is to insert coils into the tube to generate an eddy current, detect the impedance component in the direction perpendicular to the direction of coil impedance change caused by the lift-off variation between the coils and the inner surface of tube, and obtain the liner thickness on the basis of the impedance component. In a case where the lift-off variation is larger, the impedance component in the direction of coil impedance change caused by the lift-off variation is detected, so that the component is used to correct the impedance component perpendicular to the same, thereby obtaining the liner thickness in accordance with the corrected values.
37 citations
TL;DR: In this article, the effect of tensile stress on the terminal solubility of hydride-forming metal components was investigated and the results showed that hydrogen migrates up tensile strain gradients because of the effects of stress on solubilities and solusability limit.
36 citations
Patent•
03 Aug 1983TL;DR: In this article, alloys are described which contain nickel, aluminum, boron, iron and in some instances manganese, niobium and titanium, as well as other materials.
Abstract: Alloys are described which contain nickel, aluminum, boron, iron and in some instances manganese, niobium and titanium.
35 citations
Patent•
28 Jan 1983TL;DR: This article modified standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in a product having superior high temperature steam corrosion resistance.
Abstract: Modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.
Patent•
26 Apr 1983TL;DR: In this paper, a composition useful in the production of tritium in a nucleareactor was described, where lithium aluminate particles are dispersed in a matrix of zirconium.
Abstract: A composition is described useful in the production of tritium in a nucleareactor. Lithium aluminate particles are dispersed in a matrix of zirconium. Tritium produced by the reactor of neutrons with the lithium are absorbed by the zirconium, thereby decreasing gas pressure within capsules carrying the material.
TL;DR: In this article, the local environment of hydrogen and deuterium atoms dissolved in amorphous alloys with the composition ZrNi and Zr 2 Ni was studied using neutron inelastic scattering and neutron diffraction techniques.
Abstract: The local environment of hydrogen and deuterium atoms dissolved in amorphous alloys with the composition ZrNi and Zr 2 Ni was studied using neutron inelastic scattering and neutron diffraction techniques. The frequency distribution functions exhibit a broad peak at about 130 meV. Interatomic DNi and DZr correlations are observed in the radial distribution function curves at correlation lengths of 1.7 A and 2.1 A respectively for both alloy compositions. It is concluded that the majority of hydrogen and deuterium atoms in the amorphous alloys are trapped at holes in the tetrahedra which consist of three or four zirconium atoms. The maximum hydrogen content per metal atom can be explained by assuming a statistical configuration of the metal atoms.
TL;DR: In this article, the transformation sequences of amorphous Ni x Zr l−x alloys are investigated at compositions near x=0.241, 0.333 and 0.365 by means of differential scanning calorimetry (DSC).
Abstract: The transformation sequences of amorphous Ni x Zr l−x alloys are investigated at compositions near x=0.241, 0.333 and 0.365 by means of differential scanning calorimetry (DSC). The activation energies of the observed processes are calculated by means of Kissinger plots and the heats of crystallization are calculated. It is shown that the DSC method is well suited to characterize amorphous samples because it is sensitive to composition changes.
Journal Article•
TL;DR: In this article, the internal oxidation due to the reduction of the UO 2 pellets by the Zircaloy cladding material is analyzed, and a model is developed which solves only the oxygen diffusion problem in the five phases which are formed due to UO2 /Ziraloy interaction, without taking into account zirconium and uranium diffusion.
Patent•
20 Jun 1983TL;DR: A zirconium alloy having superior corrosion resistance, containing Sn of a small amount not less than the amount of Sn existing in the solid-solution of the ZIRCONIUM alloy at a room temperature, and at least one element chosen between Fe and Cr, each in a small fraction of the amount required for each of each of the two elements to be present in the solution of the alloy at room temperature is presented in this article.
Abstract: A zirconium alloy having superior corrosion resistance, containing Sn of a small amount not less than the amount of Sn existing in the solid-solution of the zirconium alloy at a room temperature, and at least one element chosen between Fe and Cr, each in a small amount not less than the amount of each of Fe and Cr existing in the solid-solution of the zirconium alloy at room temperature, the total amount of Fe and Cr existing in the solid-solution of the zirconium alloy being not less than 0.26%. the zirconium alloy being annealed after a solution heat treatment at a temperature at which both the a phase and e phase thereof are included in the zirconium alloy. Preferably, the alloy consists of 1-2% of Sn, at least one element selected from the group of 0,05 - 0,3% Fe, 0,05 - 0,2% Cr, 0 - 0,1% Ni, balance Zr.
TL;DR: In this paper, an Al-Cu-Li-Mg-Zr alloy, produced by rapidly solidified powder processing, was found to exhibit ductility improvements over comparable, lithium-containing alloys.
TL;DR: In this article, the effect of sputtered films of Nichrome, stainless steels and platinum on the oxidation behavior of Zircaloy-2 and Nissrome-4 in steam at 773 K and 10.5 MPa was investigated.
01 Jan 1983
TL;DR: In this article, the authors reviewed the use of acoustic emission (AE) techniques for studying corrosion problems and concluded that the AE method is a prommising approach to the detection and monitoring of localized corrosion in both laboratory specimens and engineering structures.
Abstract: Current theoretical and experimental research on the use of acoustic emission (AE) techniques for studying corrosion problems is reviewed. In particular, attention is given to the AE behavior of Type 304 stainless steel in aqueous environment, and a new method for analyzing corrosion, stress corrosion cracking, and corrosion fatigue in Type 304 steel is described. Results are also presented for other steels, aluminum and magnesium alloys, copper and its alloys, uranium alloys, and titanium and zirconium alloys. It is concluded that the AE method is a prommising approach to the detection and monitoring of localized corrosion in both laboratory specimens and engineering structures. Care must be taken, however, to discriminate valid AE signals from the background noise and to interpret the results correctly. 95 references.
TL;DR: In this article, an isotope dilution method combined with neutron activation analysis was applied to the determination of traces of hafnium in zirconium and Zircaloys.
Abstract: A new method, an isotope dilution method combined with neutron activation analysis, has been applied to the determination of traces of hafnium in zirconium and Zircaloys. A known amount of /sup 174/Hf-enriched hafnium solution was added to the sample as a spike. The mixture was dissolved and then irradiated in a reactor, together with natural and spike hafnium solutions. After cooling, the spiked hafnium was separated and the ..gamma..-ray spectra were measured, together with the natural and spike hafniums. The content of hafnium in the sample was calculated from the measured /sup 175/Hf//sup 181/Hf count rate ratio. A few parts-per-million of hafnium was determined with a relative standard deviation of 0.93%. The method was used to determine the value of hafnium in zirconium and Zircaloy reference materials, prepared by the National Bureau of Standards (NBS) and the Japan Atomic Energy Research Institute (JAERI). 3 figures, 4 tables.
TL;DR: In this article, the magnetic properties of amorphous alloys of the type Mg1−xNix, Zr 1−x Nix, Hf 1−−xCox, and Nb 1−XCox were studied in the temperature range 4.2-300 K. The saturation moments in these alloys and other Co-base amorphized alloys were analyzed in terms of a model proposed earlier, where account is taken of the size difference of the constituent metal atoms and the presence of compositional short-range ordering.
Abstract: The magnetic properties of amorphous alloys of the type Mg1−xNix, Zr1−xNix, Hf1−xCox, and Nb1−xCox were studied in the temperature range 4.2–300 K. The saturation moments in these alloys and other Co‐base amorphous alloys were analyzed in terms of a model proposed earlier, where account is taken of the size difference of the constituent metal atoms and the presence of compositional short‐range ordering. It is shown that an additional moment reduction can be expected in amorphous alloys in which the 3d metal is combined with Ti, Nb, Ta, W, or Mo.
Patent•
04 Jan 1983
TL;DR: An amorphous magnetic alloy having the formula Cox My Bz wherein M is zirconium, hafnium and/or titanium is defined in this paper, where the formula is Cox my bz.
Abstract: An amorphous magnetic alloy having the formula Cox My Bz wherein M is zirconium, hafnium and/or titanium. When M is hafnium or zirconium 70≦x≦80, 8≦y≦15 and 10≦z≦16. When M is titanium, 70≦x≦72, 16≦y≦25 and 4≦z≦10. When M is hafnium together with titanium and/or zirconium, 70≦x≦80, 8≦y≦20 and 5≦z≦16.
Patent•
28 Jan 1983TL;DR: In this article, the alpha zirconium alloy fabrication method was used for high temperature, high pressure steam corrosion resistance, and improved high temperature and high pressurization.
Abstract: Alpha zirconium alloy fabrication methods and resultant
products exhibiting improved high temperature, high press
ure steam corrosion resistance. The process, according to
one aspect of this invention, utilizes a high energy beam
thermal treatment to provide a layer of beta treated micros
tructure on an alpha zirconium alloy intermediate product.
The treated product is then alpha worked to final size.
According to another aspect of the invention, high energy
beam thermal treatment is used to produce an alpha
annealed microstructure in a Zircaloy alloy intermediate size
or final size component. The resultant products are suitable
for use in pressurized water and boiling water reactors.
TL;DR: In this article, a critical review of irradiation growth data for zirconium alloys together with a discussion of various operating and material factors affecting growth are presented, and implications are drawn with respect to the optimum fabrication procedures and material characteristics of zirconium alloy used for structural components in nuclear reactors.
Abstract: Irradiation growth, which is defined as irradiationinduced changes in dimensions in the absence of an applied stress, is of concern both for fuel cladding and nuclear reactor structural components such as pressure tubes and calandria tubes. A critical review is presented of irradiation growth data for zirconium alloys together with a discussion of the various operating and material factors affecting growth. Empirical and mechanistic models used to explain and predict irradiation growth are reviewed and the most applicable are identified. On the basis of the data presented, implications are drawn with respect to the optimum fabrication procedures and material characteristics of zirconium alloys used for structural components in nuclear reactors.
TL;DR: In this paper, a number of zirconium pseudobinaries of the type Zr(BxB1-x′)2 demonstrate potential for application as hydrogen storage materials.
Abstract: A number of zirconium pseudobinaries of the type Zr(BxB1-x′)2 demonstrate potential for application as hydrogen storage materials. Pseudobinaries of the above type with B = Fe,Co, B ′ = Mn, Cr, andx =0.4, 0.5, 0.6 have been investigated here and their hydrogen storage characteristics are reported. These alloys exhibit two-phase microstructures, identified as the cubic and hexagonal Laves phases. Hydrogen is absorbed into interstitial sites in the lattice with maximum capacities approaching 1.0 H-atoms per metal atom. Hydrogen capacities and hydride stabilities decrease with ‘x’. Incomplete desorption has been observed in all instances.
TL;DR: In this paper, the high-temperature internal friction of Zirconium and Zircaloy-4 was analyzed and the apparent activation enthalpy was found to be related to the grain size.
TL;DR: In this paper, an evaluation of irradiated zirconium-liner cladding for its resistance to iodine-induced stress corrosion cracking (SCC) was made, focusing on irradiation-induced hardening in zirconsium and SCC resistance in Zircaloy-2 cladding.
Patent•
13 Oct 1983
TL;DR: In this paper, the authors describe a nuclear fuel element for use in the core of a nuclear reactor having a composite container which has a substrate and a lining made of a dilute zirconium alloy, the latter being joined to the inner surface of the substrate.
Abstract: Nuclear fuel element for use in the core of a nuclear reactor having a composite container which has a substrate and a lining made of a dilute zirconium alloy, the latter being joined to the inner surface of the substrate. The lining has a thickness of about 1 to 20% of the thickness of the composite container and it contains about 0.1 to about 0.5 and preferably about 0.2 to about 0.4% by weight of niobium, the remainder being zirconium. The dilute zirconium alloy lining protects the substrate against contamination and fission products from the nuclear fuel material and protects the substrate against stress corrosion and stress corrosion cracking. The lining has a greater corrosion resistance, in particular towards oxidation by hot water and steam, than non-alloyed zirconium. The material for the substrate is selected from standard sheathing materials and is preferably a zirconium alloy having a higher alloying content than the dilute zirconium alloy of the lining.
Patent•
02 Nov 1983
TL;DR: In this paper, the authors provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance, which comprises a metallurgical gradient across the width of the tube wall.
Abstract: There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumference and a less corrosion-resistant metallurgical condition at the inner circumference. The metallurgical gradient can be generated by heating an outer circumferential portion of the tube to the high alpha or mixed alpha plus beta range while maintaining the inner surface at a lower temperature, followed by cooling of the tube.