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Zinc and Its Alloys

Description: Report issued by the Bureau of Standards discussing world production of zinc and zinc alloys. History, metallurgy, and structural properties of zinc are presented. This report includes tables, illustrations, and photographs.
Date: November 6, 1931
Creator: United States. Bureau of Standards.
Partner: UNT Libraries Government Documents Department
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Zinc-Lead-Copper Resources and General Geology of the Upper Mississippi Valley District

Description: From introduction: This report discusses the general geology of the Upper Mississippi Valley zinc-lead district, the distribution of ore deposits, and some relations of the ore deposits to the major geologic features.
Date: 1955
Creator: Heyl, Allen V.; Lyons, Erwin J.; Agnew, Allen F. & Behre, Charles H., Jr.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Sheet and Strip Material

Description: Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Wire Material

Description: Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Sheet and Strip Material

Description: Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department

Zircaloy-4 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: unknown
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-4 Wire Material

Description: Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy Cladding Thickness Testers

Description: Technical report. From Abstract : "A number of similar eddy current instruments were developed to measure the thickness of Zircaloy over uranium metal in the range of 5 to 25 mils, Zircaloy over UO2 in the range of 20 to 40 mils, and the wall thickness of Zircaloy tubes in the range of 20 to 40 mils. The instruments were designed for use with hand-held probes or with feeder-mounted probes to measure the inside and outside cladding thickness of tubular elements and the wall thickness of Zircaloy… more
Date: December 1961
Creator: Goodwin, Leslie E.
Partner: UNT Libraries Government Documents Department
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Zircaloy Process Tube Monitoring

Description: The large scale application of Zircaloy-2 pressure tubes for structural use either in or out of reactor service, is without precedent. For more common materials, there normally are adequate data and long operating histories on which to base design and service limits. In the absence of such information for Zr-2, several investigative programs have been devised to provide much of the information from which design and service limits may be defined for Zr-2 pressure tubes. These investigations enco… more
Date: April 11, 1960
Creator: Pankaskie, P. J.
Partner: UNT Libraries Government Documents Department
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Zircex Kinetics And Uranium Loss Study

Description: "A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented."
Date: November 13, 1957
Creator: Carter, Jr, T. J. & Stone, R. A.
Partner: UNT Libraries Government Documents Department
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Zircex Uranium Sublimate Loss

Description: "One of the limitations of the Zircex Process is the large percentage loss of U which is carried off with the volatile ZrCl/sub 4/. Since the ratio of U to Zr in the fuel element is quite small (< 1%), a large percentage of U loss can be caused by small amounts of U in the ZrCl/sub 4/ sublimate. The U loss must be kept below 1% if the Zircex Process is to be adapted to industrial scale processing."
Date: January 24, 1958
Creator: Jaworowski, T. R. & King, III, C. J.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: 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-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Description: 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 … more
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Partner: UNT Libraries Government Documents Department
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Zirconium Metal Fines Recovery: Interim Technical Report for May 15, 1950 to December 15, 1950

Description: 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.
Partner: UNT Libraries Government Documents Department
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Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions

Description: The following report studies an estimation of the amount of Pu(III) and Pu(IV) present in the IBP Stream, with the purpose of establishing an analytical, method suitable for routine control analysis. A method is discussed that is based on carrying Pu(IV) upon a zirconium phanylarsonate precipitate.
Date: June 30, 1948
Creator: Ice, C. H.
Partner: UNT Libraries Government Documents Department
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