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Flow Characteristics of a Circular Weir in a Centrifugal Field

Description: Technical report outlining the use of circular weirs in solvent extraction between liquid phases of nuclear fuel elements. From Abstract : "A correlation of the experimental coefficients was developed to allow calculation of general weir performance."
Date: June 1961
Creator: Webster, Donald S.; Williamson, Clifton L. & Ward, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nonlinear Analogue to Digital Converter

Description: Technical report. From Abstract: "An electromagnetical instrument is described which produces a shaft rotation which is a linear function of the quantity being measured from a non-linear input signal. The instrument was used to convert the output function of the Nuclear Test Gage (NTG) which is nonlinear with respect to fuel concentration to a form that will directly drive an automatic production recorder (APR). The output shaft is also geared to a Veeder Root counter so that the value of the i… more
Date: August 1959
Creator: Goodwin, Leslie E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Np237 and Pu238 From Irradiated Neptunium Oxide

Description: Technical report. From Abstract: "An ion exchange process was demonstrated for the recovery of Pu238 from irradiated neptunium oxide. Three cycles of anion exchange proved adequate for the removal of fission products and for the separation of the neptunium and plutonium from each other."
Date: November 1959
Creator: Burney, Glenn A. & Prohaska, Charles A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ultrasonic Energy Applied to Aluminum Extrusion Cladding of Tubes

Description: Technical report. From Abstract: "Ultrasonic energy appropriately applied to the die or container of a laboratory-type direct extrusion press effected a marked increase in the free extrusion rate of lead and aluminum billets at a constant extrusion rate. the same results were obtained in extrusion cladding steel tubes with aluminum. Rate increases were generally 100 per cent or greater, and decreases in force were usually within the range of 10 to 20 per cent. Furthermore, the shape and slope o… more
Date: November 1959
Creator: Jones, J. Byron; DePrisco, Carmine F.; Maropis, Nicholas & Thomas, John G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Oxidation of Neptunium(V) by Vanadium(V)

Description: Technical report. From Abstract: "Rate data are presented for the oxidation of neptunium (V) by vanadium (V) in nitric acid." From Summary: "Rates of oxidation of neptunium (V) were determined by a solvent extraction technique based on the difference in distribution coefficients for neptunium (V) and neptunium (VI)."
Date: November 1959
Creator: Dukes, Ernest K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mounting Thermocouples on SPERT Test Assemblies

Description: Technical report. From Abstract: "A method of fastening thermocouples to 0.030-inch-thick aluminum cladding on test fuel elements was developed. The installation does not lead to hot spots by the addition of extra metal of the distortion of the cooling water channels. Fuel element temperatures were faithfully followed in SPERT tests up to the melting point. The method has been useful for fastening thermocouples to aluminum sections in general."
Date: December 1959
Creator: Sanders, Harold S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coextrusion of Powder-Compact Slugs

Description: Technical report. From Abstract: "A process was developed for manufacturing aluminum-clad slugs containing UO2 or ThO2 dispersed in an aluminum matrix. In this process a mixture of the oxide and aluminum powder is cold compacted to form the billet core, which is then coextruded with an aluminum sheath to produce the clad slug."
Date: April 1960
Creator: Marsh, Harold G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anion Exchange Recovery of Plutonium From Reduction Residues

Description: Technical report. From Abstract: "An anion exchange process was demonstrated for the recovery of plutonium from waste produced in the reduction of plutonium salts to the metal. Plutonium in a highly salted 6M nitric acid solution derived from the dissolution of slag and crucible waste was separated from impurities by absorbing the Pu (IV) nitrate complex on the anion exchange resin and subsequently eluting with nitric acid. A flowsheet for plant operation is presented."
Date: February 1960
Creator: Russell, Edwin R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Neptunium From Purex Waste by an Agitated Bed of Anion Exchange Resin

Description: Technical report. From Abstract: "Data are presented for the absorption of thorium and neptunium from synthetic waste concentrate of the "Purex" process by a miniature agitated bed of anion exchange resin. The behavior of neptunium indicated that efficient recovery should be obtained from Purex high activity waste concentrate by this technique. A method was developed for calculating absorption losses from agitation beds of resin. The predicted losses were in excellent agreement with experimenta… more
Date: February 1960
Creator: Prout, William E., 1921- & Fernandez, LeVerne P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Data From a Mockup of the HWCTR Lattice in the PDP

Description: Technical report. From Abstract: "Experiments were performed in the Process Development Pile (PDP) with a critical mockup of the Heavy Water Components Test Reactor (HWCTR) lattice. Reactivity measurements served to determine control rod worths, the temperature coefficient of the reactor at low temperatures, the dependence of keff on concentrations of U235 and poisons in the "driver" region of the reactor, and the changes in keff that occur in certain conceivable accidents in the HWCTR. Flux di… more
Date: February 1960
Creator: Graves, William E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of Aluminum-Lithium Alloys Containing Up to 8% Lithium

Description: Technical report. From Abstract: "The thermal conductivities of aluminum-lithium alloys containing up to * wt % lithium were determined at temperatures between 125 and 260ºC. The addition of lithium to aluminum sharply reduces the conductivity from 0.60 cal/(sec)(ºC)(cm) for pure aluminum to 0.22 cal/(sec)(ºC)(cm) for 2 wt % alloys; further addition linearly and more gradually decreases the conductivity to 0.16 cal/(sec)(ºC)(cm) for a 7.9 wt % alloy."
Date: April 1960
Creator: Costas, Louis P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Automatic Dose Computer for Radiation Film Badges

Description: Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."
Date: April 1960
Creator: Davis, John E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Swaging of Uranium Dioxide Tubes - [Part] I

Description: Technical report. From Abstract: "A method was developed for fabricating tubular fuel elements of uranium dioxide by swage compaction of crushed, fused UO2. The elements were 5 to 10 feet long and were clad with stainless steel. UO2 densities up to 91% of theoretical were obtained in tubes about 2.1 inches in outside diameter and 0.3 inch in wall thickness."
Date: August 1960
Creator: Ferrara, Anthony S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutron Spark Counter

Description: Technical report. From Abstract : "Spark counters of the wire plate type are rugged and simple, and their sensitivity is directly proportional to the specific ionization of incident particles. Spark counters are insensitive to beta and gamma radiation but readily respond to alpha particles. With a suitable converter, the spark counter can also be employed as a neutron counter. Spark counters thus appear to be very good candidates for the measurement of neutron flux at reactor startup, where the… more
Date: October 1960
Creator: Caiati, Frank P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anion Exchange of Neptunium in Nitrate Solutions

Description: Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."
Date: December 1960
Creator: Burney, Glenn A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of Amides as Extractants

Description: Technical report. From Abstract : "Laboratory data are given and discussed that outline the potential application of N, N-distributed amides to the separation of uranium, neptunium, and plutonium from fission products."
Date: January 1961
Creator: Siddall, Thomas H., III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium From Metallurgical Reduction Residues

Description: Technical report. From Abstract : "A semicontinuous process was developed for dissolving the solid residues that are produced in the calcium reduction process for converting plutonium fluoride to plutonium metal. The slag and crucible residues are charged to a column-type dissolver, and are there exposed to a flowing solution of hot nitric acid followed by a nitric acid - aluminum nitrate solution. The resultant solution is suitable as feed for an ion exchange process for recovering plutonium."
Date: June 1961
Creator: Dukes, E. Kenneth & Prout, William E., 1921-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extrusion of Uranium Tubes

Description: Technical report. From Abstract : "Several hundred long, thin-walled uranium tubes were extruded to close dimensional tolerance by a potentially low cost fabrication process in commercial facilities. The principal process steps were; forging uranium ingots, machining the forged ingots into billets, and extruding the billets into tubes. Some 750 tubes (maximum dimensions: 3.5 inches in diameter and 15 feet long) were fabricated by this process. Dimensional control was excellent in that 88% of th… more
Date: July 1961
Creator: Fisher, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Precipitation of Neptunium Peroxide

Description: Technical report. From Abstract : "Optimum conditions were determined for the precipitation of neptunium (IV) peroxide from nitric acid solutions. The results indicate that the precipitation could be applied successfully on a plant scale. ... Two crystalline modifications of the peroxide were prepared; these two crystalline structures were similar to structures previously reported for plutonium peroxide."
Date: July 1961
Creator: Burney, Glenn A. & Dukes, Ernest K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Identification of Curium-242 in Irradiated Neptunium

Description: Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."
Date: August 1961
Creator: Carothers, Glenn A.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of UO2 Fuel Elements by Vibrational Compaction

Description: Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution,… more
Date: February 1962
Creator: Marah, Harold G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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