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Zirconium Highlights

Description: The testing of Zircaloy at various stages of processing by ultrasonic techniques is described A study was made to determine the feasibility of substituting ammonium bifluorlde for the liquid hydrofluoric acid generally used in the etching processes required for the fabrication of Zircaloy fuel coniponents The addition of B to Zr results in a very strong alloy however. they show little proniise for being ductile. Zirconium-boron alloys can be hot forged Boron is very detrimental to the oxidation… more
Date: January 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zirconium hydride formation in Hanford production reactor process tubes

Description: Examination of Zircaloy-2 process tubes from Hanford Production Reactors has revealed extensive zirconium hydride formation. In general, attack is limited to the downstream portions of tubes where aluminum spacers are located. Most of the hydride platelets are contained in a case or layer on the inner surface of the tube. It is not unusual to find cases 0.004 to 0.005 in. thick. Analyses of the 0.037 in. wall tubes with such cases intact often reveal hydrogen concentrations greater than 1000 pp… more
Date: December 1, 1967
Creator: Winegardner, W. K. & Griggs, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Zirconium-Hydrogen System at High Hydrogen Contents

Description: In order to elucidate the phase diagram of the Zr--H system at high hydrogen contents, a pressure-compositiontemperature study of this system in the temperature range 550 to 850 deg C was carried out from ZrH to ZrH/sub 2/. From the obtained isotherms, the position of the boundary between the two-phase ( beta + delta ) region and the single phase delta region was more precisely defined (where beta designates the hydrogen stabilized high temperature zirconium phase, and delta the cubic hydride p… more
Date: June 30, 1960
Creator: Libowitz, G. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zirconium tube sample evaluation program

Description: This document, dated May 3, 1966, presents data from the zirconium tube sample evaluation program at the Hanford Reservation. Data presented includes: (1) operating history, (2) flow characteristics, (3) time in core, and (4) average temperature for numerous samples. The document consists entirely of data.
Date: May 3, 1966
Creator: Korpi, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Zirflex Decladding of Tube-in-Tube Type Fuel Elements

Description: Pilot unit Zirflex dissolutions were carried out on near prototypical tube-in-tube type elements clad in oxidized Zircaloy. The runs were made with the elements horizontal and at simulated large scale operating conditions. No significant difference was noted between the actual decladding achieved in these experiments and that which was predicted from prior studies on similarly oxidized elements with somewhat different geometries. No gas blanketing nor diffusion effects were observed. Initially,… more
Date: February 23, 1961
Creator: Smith, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE ZIRFLEX PROCESS TERMINAL DEVELOPMENT REPORT

Description: The Zirflex Process employs a boiling aqueous solution of ammonium fluoride and ammonium nitrate to dissolve zirconium or Zircaloy. Average unoxidized Zircaloy dissolution rates are from 10 to 15 mils/hr for the optimum charge solution of 5.5M NH/sub 4/F-0.5M NH/sub 4/NO/sub 3/ at a F/Zr mole ratio of 7. Zircaloy, which is oxidized by exposure to high-temperature air or water, dissolves at rates of threeto five-fold less. Cores of uranium, uranium- aluminum, and uranium dioxide are not severely… more
Date: September 20, 1960
Creator: Smith, P.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ZORCH--AN IBM 7090 PROGRAM FOR THE ANALYSIS OF SIMULATED MSRE POWER TRANSIENTS WITH A SIMPLIFIED SPACE-DEPENDENT KINETICS MODEL

Description: A program (ZORCH) is described which is an extended and revised version of the point-model kinetics program MURGATROYD. A model is used in which the axial space dependence of the fuel and graphite temperatures is calculated, and the effect on reactivity of deviations from the steady state values is assumed to be given by the product of an appropriate temperature coefficient of reactivity times the deviations from the steady state value of the nuclear average temperature (NAT). The NAT is comput… more
Date: September 18, 1962
Creator: Nestor, C. W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE ZrO$sub 2$-CaO-UO$sub 2$ CERAMIC FUEL FABRICATION FOR THE EBWR SPIKED CORE ELEMENTS. Final Report-Metallurgy Program 7.9.5

Description: A series of experiments was proposed in which the thermal output of the EBWR is increased to 100 Mw. The increase in thermal enengy will be accomplished by inserting 32 spike elements in the initial fuel core. The fuel selected for the spike elements was a cubic solid solution in the system ZrO/sub 2/- CaO- UO/ sub 2/. The ceramic fuel was fabricated in the form of pellets by compacting a mixture of U/sub 3/O/sub 8/, CaCO/sub 3/, and ZrO/sub 2/. The pressed pellets were sintered in air at 1675 … more
Date: May 1961
Creator: Lied, R. C.; Lynch, E. D. & Handwerk, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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