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19,303 Matching Results
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ZIRCONIUM ALLOYS FOR NUCLEAR REACTOR APPLICATIONS
None
Date:
June 11, 1952
Creator:
Schwope, A.D. & Chubb, W.
System:
The UNT Digital Library
Zirconium analysis
Recent attempts to displace fixed plutonium from the body by zirconium therapy have made an analytical method for the determination of zirconium in urine salts advisable. Standard chemical analytical methods for zirconium in rock were not adaptable to urine salts. The poor results obtained from these standard methods necessitated the development of a modified analytical procedure. The results of this work are reported herein.
Date:
February 21, 1950
Creator:
Thorburn, R. C.
System:
The UNT Digital Library
ZIRCONIUM CLADDING OF URANIUM
Under proper conditions of vacuum and mold preheat, a sound ductile alloy bond can be achieved by casting molten uranium into zirconium and Zircaloy- 2 molds. Investigations indicate that a process for production of zirconium of Zircaloy-2 clad fuel elements can be developed by casting directly into preformed shells. Employment of cast bonding techniques appears to be a simple and practical method for assembling extrusion billets. It also appears that coextrusion of cast bonded normal uranium billets produces a clad rod exhibiting a rather uniform cladding thickness and map permit greater freedom in selection of extrusion conditions to produce a clad and bonded geometry. Forming of cast bond ingots in diamond-round or oval-round sequences falled to produce a clad rod with uniform jacket thickness. subsequent forming operations failed to rectify nonuniformities in jacket thicknesses once they had occurred. (auth)
Date:
November 1, 1954
Creator:
Pankaskie, P. J. & Schaffer, L. D.
System:
The UNT Digital Library
Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel
The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-treated plates demonstrated that none of the systems were metallurgically stable. The instability was generally manifested by the (1) interaction of the discrete boron compounds with the matrix and (2) precipitation of a hypothetically boron-rich phase throughout the stainless steel matrix material.
Date:
July 31, 1959
Creator:
Cherubini, Julian H. & Leitten, C. F., Jr.
System:
The UNT Digital Library
Zirconium Diboride, Boron Nitride, and Boron Carbide Compatibility With Austenitic Stainless Steel
The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000 to 12OO deg C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-treated plates demonstrated that none of the systems was metallurgically stable. The instability was generally manifested by the interaction of the discrete boron compounds with the matrix and precipitation of a hypothetically boron-rich phase throughout the stainless steel matrix material. Of the three compounds, boron nitride was relatively the most stable in a stainless steel matrix under the test conditions. (auth)
Date:
July 31, 1959
Creator:
Cherubini, J. H. & Leitten, C. F. Jr.
System:
The UNT Digital Library
Zirconium Fire and Explosion Hazard Evaluation. Interim Report
None
Date:
August 1, 1956
Creator:
unknown
System:
The UNT Digital Library
ZIRCONIUM FLUORIDE PHASE STUDIES. I. A PRELIMINARY INVESTIGATION OF SOLID PHASES
Solid phases in the zirconium-nitric acid-hydrofluoric acid system were identified by chemical and x-ray diffraction methods. Five different compounds were crystallized at various temperatures and fluoride concentrations from fluoride or fluoborate solutions. These include the mono- and trihydrates of zirconium tetrafluoride, plus three hydrolysis products which possess a fluoride- to-zirconium ratio of approximately three, yet produce different x-ray patterns. The trifluorides crystallize from solutions of low fluoride-to-zirconium ratio at temperatures of below 90, 65 to 100, and above above 95 deg C, respectively. Solubilities of these basic trifluorides were measured at 25 deg C in 1, 6, and 16M nitric acid. (auth)
Date:
January 15, 1959
Creator:
Chapman, A.G. & Woodriff, R.A.
System:
The UNT Digital Library
Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report
Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date:
November 17, 1955
Creator:
Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
System:
The UNT Digital Library
ZIRCONIUM HAZARDS RESEARCH. Progress Report No. 1 for September 1, 1956 to February 28, 1957
None
Date:
February 28, 1957
Creator:
Herickes, J.A. & Richardson, P.A.
System:
The UNT Digital Library
Zirconium Hazards Research. Summary Report No. 3655 for September 1, 1956 to August 31, 1957
The sensitivity characteristics of a variety of Zr samples such as sponge, scrap, powder and process materials were studicd. Of particular interest was the determination of the relative seasitivity of these materials to such stimuli as impact, friction, electrostatic discharge, and heat. A study of the zirconium--water reaction at relatively low temperature was initiated. In general, scrap and sponge were relatively insensitive to impact. Only one proeess material, the distillation residue, exhibited any pyrophoric tendencies in this test. As anticipated, the majority of the samples tested were somewhat sensitive to friction. The dry distillation residues and Ca-reduced Zr powders, which had frequency rates of 100% in most cases, were the most sensitive of all the samples tested. Sponge was moderately sensitive, but the variation in sensitivity could not be correlated with either particle size or chemical impurities. Neither the Zr or Zircaloy scraps in the form of chips and turnings were very sensitive. The maierial which proved to be most insensitive to friction was the vapor phase residue. A frequency rate of zero was noted for all the samples tested. Using a condenser discharge to heat wire samples rapidly in aa inert atmosphere to a temperature well above the melting …
Date:
August 31, 1957
Creator:
Herickes, J.A.; Richardson, P.A.; Weiss, M. & Gelernter, G.
System:
The UNT Digital Library
Zirconium Highlights
The effect of hot-worked thickness on the corrosion behavior of atmosphere-melted Zircaloy-2 is discussed. Hydrogen pickup upon etching Zircaloy- 2 Zircaloy-3, and properties of vacuum-cast Zircaloy-2 and the fabrication of special Zirccaloy shapes are presented. A hardness converison chart for annealed zirconium and zirconium alloys is included. (J.E.D.) The useful properties of the tungsten wires used in the incandescent lamp and ra dio tubes industry are ensured by adding about 1% of various ingredie (e.g., K, Na, Al, Si compounds) to the tungstic acid and producing metal powder and compressed rods. During the sintering of these rods, the additions are evapo rated to such an extact that finally the concentration of foreign atoms remains only 10/sup 5/. According to the investigations, the warm hardness values of these tungsten pieces is determined by the traces of impurities. In order to investigate the influencce of the various kinds of atoms, an apparatus was built for the determination of half-micro warm hardnesses of various kinds of tungsten metals in the temperature interval 20 to 800 deg C The tungsten wires made with additions containing Si had an average hardness H/sub V/ = 250 at 800 deg C, while the wires without such additions …
Date:
August 1, 1958
Creator:
unknown
System:
The UNT Digital Library
Zirconium: Its Production and Properties
Report concerning the element Zirconium that provides extensive details regarding its acquisition and production.
Date:
1956
Creator:
United States. Bureau of Mines.
System:
The UNT Digital Library
Zirconium Metal Fines Recovery: Interim Technical Report for May 15, 1950 to December 15, 1950
This report covers the laboratory and pilot plant investigation of the reclamation of the low hafnium zirconium fines resulting from the manufacture of zirconium sponge and zirconium crystal bar. The process investigated involved recovery of the zirconium as zirconium tetrachloride, by drying the fines in an atmosphere of nitrogen and subsequent chlorination of the fines with anhydrous hydrogen chloride at temperatures above the sublimation point of the product.
Date:
January 24, 1951
Creator:
Ogburn, S. C., Jr. & Reader, L. J.
System:
The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report
The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date:
September 20, 1951
Creator:
Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System:
The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report
The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
Date:
November 20, 1951
Creator:
Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System:
The UNT Digital Library
Zirconium Pilot Plant Research and Development. Progress Report
A summary of the work which was done on the small pilot plant during the week's operation shows the following: (1) High vaporization rates can be obtained from a vibrating flash plate. (2) Feeding powder to the plate at a constant and controllable rate presented some difficulty. This may be overcome by pumping between Victoprene seals, proper outgassing of the powder, using a smaller diameter screw, and sloping the feed screw upward to avoid translation of the powder by vibration. (3) Deposition rates could not be properly studied because of high noncondensable pressures. There is an indication that too high a flow rate favors the deposition of ZrI/sub 2/ if the filiment temperature is too low. (4) No corrosion of the flash plate was evidenced during the short period the plant was in operation. A thorough study of corrosion must be made, however, since the entire process may depend on the durability of the flash plate. (5) This type of equipment offers a means of rapidly obtaining good data at a low cost on the fundamentals of an iodide-flow process for the production of zirconium metal. (auth)
Date:
November 20, 1951
Creator:
Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System:
The UNT Digital Library
Zirconium-Precipitation Pilot Plant
This report follows an investigation with the objectives to improve the design of an existing pilot plant to allow better control of operating variables than was attained by previous investigators, and to determine the effect of leaching time on phthalate recovery.
Date:
September 30, 1950
Creator:
Parish, G. T.; Bakal, R.; Goodman, E. I. & Larsen, H. A.
System:
The UNT Digital Library
Zirconium Purification Pilot Plant
This report discusses the process of zirconium purification, providing an alternate method for converting ZrCl4 solution to the oxide in order to free it from small amounts of hafnium impurity that are naturally present.
Date:
September 12, 1950
Creator:
Lea, D. C.; Aykanian, A. A.; Abbanat, R. G. & Bowman, W. H.
System:
The UNT Digital Library
Zirconium Research and Development : Progress Report
From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date:
October 15, 1950
Creator:
Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
System:
The UNT Digital Library
ZIRCONIUM RESEARCH AND DEVELOPMENT. Progress Report No. 9 for September 15, 1950 to October 15, 1950
A zirconium crystal bar, weighing 29 pounds and 1 5/16 inches in diameter by 8 feet in over-all length, was prepared, using pear-shaped zirconium couples to join the filament to the electrodes. This crystal bar was the largest produced to date in the 16-in.-diam. de Boer unit. The design of the couplings was modified to incorporate improvements indicated by the initial run, and another run is in progress. Binary alloys of Zr and Ni, Cr, and Si, as well as a zirconium alloy containing Fe, Al, and Si, were prepared for use as feed material in the small pyrex de Boer bulbs. The transfer of these elements from the feed to the crystal bar is being investigated. The rate of deposition and the type of crystal structure obtained with additions of various amounts of iodine are being studied. (auth)
Date:
October 15, 1950
Creator:
Bulkowski, H.H.; Sebenick, J.J.; Campbell, I.E. & Gonser, B.W.
System:
The UNT Digital Library
Zirconium Tube Rupture from Localized Overheating
Very little information and data are available on the various physical properties of Zircaloy tubing, especially the high temperature- high pressure failure aspects. As greater use is being made of the low cross-sectional properties of this material in the design and development of reactor components, it was considered desirable to determine the type of failure that would be experienced under conditions of a localized over-heating. This hot-spot could be caused by "cocked" or warped fuel elements coming in direct contact with the process tube, thereby preventing adequate cooling media at the particular location.
Date:
September 9, 1959
Creator:
Jackson, P. M.
System:
The UNT Digital Library
THE ZIRCONIUM-URANIUM DIOXIDE REACTION
None
Date:
July 22, 1957
Creator:
Mallett, M.W.; Droege, J.W.; Gerds, A.F. & Lemmon, A.W. Jr.
System:
The UNT Digital Library
Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements
A study was conducted to compare the estimated dissolution rate of Zircaloy-2 clad annular fuel elements on the fully expesed metal with that in the annuli. Results indicate that decladding of these elements should proceed uniformly on all surfaces. Heat balance data from the study are also reported. (J.R.D.)
Date:
December 1, 1959
Creator:
Smith, P. W.
System:
The UNT Digital Library
Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements
The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Date:
December 9, 1959
Creator:
Smith, P. W.
System:
The UNT Digital Library