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19,012 Matching Results
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Zircaloy-4 Sheet and Strip Material
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.
System:
The UNT Digital Library
Zircaloy-4, Uranium Dioxide, and Materials Formed by Their Interaction. A Literature Review With Extrapolation of Physical Properties to High Temperatures.
None
Date:
January 1, 1967
Creator:
Hammer, R. R.
System:
The UNT Digital Library
Zircaloy-4 Wire Material
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.
System:
The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 1, November 1967--January 1968.
None
Date:
January 1, 1968
Creator:
Megerth, F. H.
System:
The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 2, February 1968--April 1968.
None
Date:
January 1, 1968
Creator:
Megerth, F. H.
System:
The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 4, August--October 1968.
None
Date:
January 1, 1968
Creator:
Megerth, F. H.
System:
The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 5, November 1968--January 1969.
None
Date:
January 1, 1969
Creator:
Megerth, F. H.
System:
The UNT Digital Library
Zircaloy-Clad UO$Sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 8, August--October 1969.
None
Date:
January 1, 1969
Creator:
Megerth, F. H.
System:
The UNT Digital Library
Zircaloy-Clad UO2 Fuel Rod Evaluation Program. Quarterly Progress Report Nos. 6 and 7, February--July 1969
None
Date:
December 31, 1969
Creator:
Megerth, F. H.
System:
The UNT Digital Library
Zircaloy Cladding Thickness Testers
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 sheaths. The instruments have a sensitivity of 3 microamps per mil change in Zircaloy thickness and an accuracy of +/- mil."
Date:
December 1961
Creator:
Goodwin, Leslie E.
System:
The UNT Digital Library
Zircaloy Pickle Bath Salts. Chemical Nature and Thermal Decomposition of Hydrated Zirconium Fluoride
None
Date:
January 1, 1962
Creator:
Rynasiewicz, J.
System:
The UNT Digital Library
Zircaloy Process Tube Monitoring
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 encompass in-and-out-of-reactor creep and stress-rupture testing, pre-and-post irradiation testing, and bust strength, as well as the effect of flaws or defects (from both fabrication and service origins) on burst strength and fracture characteristics. Already creep and stress rupture testing of unirradiated Zircaloy-2 is well advanced, and some experimental pre-irradiation burst testing has been carried out and will be extended rapidly as improved equipment becomes available. One irradiated KER tube sample has been burst tested and the requirement for post irradiation burst testing equipment have been defined.
Date:
April 11, 1960
Creator:
Pankaskie, P. J.
System:
The UNT Digital Library
Zirconium Alloys for Steam Service: a Preliminary Study
The fabricability, elevated temperature strength, steam corrosion resistance, and hydrogen pickup of various binary, ternary, and quaternary alloys were studied experimentally.
Date:
June 24, 1960
Creator:
Klepfer, H. H.
System:
The UNT Digital Library
ZIRCONIUM ELECTROPLATING ON URANIUM FROM MOLTEN ALKALI FLUORIDE SALTS.
None
Date:
January 1, 1968
Creator:
Nissen, D.A. & Stromatt, R.W.
System:
The UNT Digital Library
Zirconium Highlights
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 behavior of Zircaloy-2. (W.L.H.)
Date:
January 1, 1960
Creator:
unknown
System:
The UNT Digital Library
Zirconium hydride formation in Hanford production reactor process tubes
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 ppM. Investigation indicates that the hydriding is the result of galvanic contact between aluminum and Zircaloy-2. The galvanic couple (contact between dissimilar metals in the presence of reactor cooling water which serves as the electrolyte) results in the cathodic charging of hydrogen into the Zircaloy.
Date:
December 1, 1967
Creator:
Winegardner, W. K. & Griggs, B.
System:
The UNT Digital Library
The Zirconium-Hydrogen System at High Hydrogen Contents
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 phase). The isotherm also show no evidence of a two-phase hydride region (cubic + tetragonal hydrides coexisting) in this temperature range, as has been observed at room temperature. (auth)
Date:
June 30, 1960
Creator:
Libowitz, G. G.
System:
The UNT Digital Library
ZIRCONIUM PROCESSING CAPABILITY OF THE IDAHO CHEMICAL PROCESSING PLANT
None
Date:
October 1, 1964
Creator:
Bower, J.R.
System:
The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant
Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date:
October 1964
Creator:
Bower, J. R.
System:
The UNT Digital Library
Zirconium tube sample evaluation program
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.
System:
The UNT Digital Library
The Zirflex Decladding of Tube-in-Tube Type Fuel Elements
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, preferential attack was noted on areas where oxide film had been scratched or handled. However, near the end of a run a random distribution of undissolved cladding existed; 90% of the cladding was removed in 6.5 hours. (auth)
Date:
February 23, 1961
Creator:
Smith, P. W.
System:
The UNT Digital Library
THE ZIRFLEX PROCESS TERMINAL DEVELOPMENT REPORT
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 attacked by the Zirflex decladding solutions. Only the soluble uranium enters the waste, with losses varying from 0.3 to 3.0 g/l. The Zirflex waste solution is neutralized to a pH of 10 before storage. This requires approximately 0.07 gallon of 50% caustic per gallon of decladding solution. The neutralized waste consists of nearly 20 vol.% of rapidly settling solids, which are easily slurried under turbulent flow conditions. These solids tend to settle out in streamline flow and therefore agitation is required during temporary storage. Conventional nitric acid core dissolution is generally applicable to Zircaloy-clad uranium and UO/sub 2/ elements since the core material is essentially free from zirconium. The addition of aluminum nitrate to the nitric acid dissolvent at an aluminum/ residual …
Date:
September 20, 1960
Creator:
Smith, P.W.
System:
The UNT Digital Library
ZODIAC(2 + 2): A REVISION TO ZODIAC2.
None
Date:
January 1, 1967
Creator:
Holeman, R. H. & Matsumoto, D. D.
System:
The UNT Digital Library
Zone Refining Applied to a Bismuth--Tin System.
None
Date:
January 1, 1967
Creator:
Land, J. S.; Smutz, M. & Burnet, G.
System:
The UNT Digital Library