Shearing Irradiated Uranium Plates (open access)

Shearing Irradiated Uranium Plates

From abstract: "Natural uranium plates that were irradiated to 600 and 1500 MWD/T were cut under water by a guillotine-type shear. Irradiation reduced the force required for shearing to 50 per cent of that required for unirradiated uranium. Measurements were made of radioactivity released to treated and untreated water in which the cut sections were stored."
Date: November 1956
Creator: Delicate, W. Scott; Osterman, Edmund J.; Zeh, Carl W. & Wither, W. T.
System: The UNT Digital Library
Spectrophotometric Determination of Mixtures of Neptunium(Iv) and Neptunium(v) in Nitric Acid Solutions (open access)

Spectrophotometric Determination of Mixtures of Neptunium(Iv) and Neptunium(v) in Nitric Acid Solutions

Technical report. From Abstract : "The concentrations of Np(IV) and Np(V) ions in nitric acid solutions were determined quantitatively by a spectrophotometric method."
Date: December 1960
Creator: Dukes, E. K. & Shuler, W. E.
System: The UNT Digital Library
Recovery of Plutonium From Metallurgical Reduction Residues (open access)

Recovery of Plutonium From Metallurgical Reduction Residues

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-
System: The UNT Digital Library
Formation of Hydrazoic Acid From Hydrazine in Nitric Acid Solutions (open access)

Formation of Hydrazoic Acid From Hydrazine in Nitric Acid Solutions

Technical report. From Abstract : "A study was made of the kinetics and stoichiometry of the formation of hydrazoic acid in nitric acid solutions containing hydrazine and ferrous sulfamate. The data were used to establish safe limits for the use of hydrazine in process solutions."
Date: September 1962
Creator: Dukes, E. Kenneth & Wallace, Richard M.
System: The UNT Digital Library
Oxidation of Neptunium(V) by Vanadium(V) (open access)

Oxidation of Neptunium(V) by Vanadium(V)

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.
System: The UNT Digital Library
Swaging of Uranium Dioxide Tubes - [Part] I (open access)

Swaging of Uranium Dioxide Tubes - [Part] I

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.
System: The UNT Digital Library
Extrusion of Uranium Tubes (open access)

Extrusion of Uranium Tubes

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 the tubes were within +/- 0.010 inch of average dimensions over their entire length."
Date: July 1961
Creator: Fisher, R. E.
System: The UNT Digital Library
A Detector for Sub-Surface Cracks (open access)

A Detector for Sub-Surface Cracks

From abstract: "An instrument was developed to detect cracks within 1/8 inch of the surface of cylindrical uranium fuel slugs. The instrument measures changes in eddy currents that are induced at a frequency of 2 KC."
Date: August 1954
Creator: Goodwin, L. E.
System: The UNT Digital Library
Nondestructive Measurement of the Uranium Content Uranium-Aluminum Alloys (open access)

Nondestructive Measurement of the Uranium Content Uranium-Aluminum Alloys

From abstract: "An instrument is described which measures the uranium content of a 0.080-inch thick plate of uranium-aluminum alloy. The content is measured by gamma-ray transmission to an accuracy of +/- 0.0006 gram per square centimeter over the range of 0.085 to 0.115 gram per square centimeter of contained uranium."
Date: October 1955
Creator: Goodwin, L. E.
System: The UNT Digital Library
Nonlinear Analogue to Digital Converter (open access)

Nonlinear Analogue to Digital Converter

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 independent variable is given to the NTG operator in digital form. A rate-of-change detector automatically trips the APR when the reading has come sufficiently close to equilibrium."
Date: August 1959
Creator: Goodwin, Leslie E.
System: The UNT Digital Library
Zircaloy Cladding Thickness Testers (open access)

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
Physics Data From a Mockup of the HWCTR Lattice in the PDP (open access)

Physics Data From a Mockup of the HWCTR Lattice in the PDP

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 distribution measurements were made to determine over-all flux shapes, local flux variations around individual components, azimuthal flux variations due to asymmetrical combinations of control rods, and vertical flux variations obtainable through the use of control rods of partial length. Sufficiently detailed flux measurements were made to permit the calculation of neutron economy tables and to determine the neutron leakage from the reactor. Suitable adjustments in the input parameters made it possible to fit the experimental results with a two-group calculation."
Date: February 1960
Creator: Graves, William E.
System: The UNT Digital Library
Summary Report on Thorium Metal Quality for Production Reactor Use (open access)

Summary Report on Thorium Metal Quality for Production Reactor Use

From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as the final step has contributed much to the production of thorium of excellent quality for reactor use."
Date: July 1958
Creator: Hayes, Edgar E.
System: The UNT Digital Library
Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions (open access)

Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

Technical report. From Abstract: "Precipitation of manganese dioxide in solutions of uranium-aluminum alloy effected maximum removal of fission products when the alloy solutions were acid deficient. Minimum adsorption of uranium and minimum volume of centrifuged MnO2 were obtained by precipitation in acidic solutions with vigorous agitation."
Date: February 1959
Creator: Henry, Hugh E.
System: The UNT Digital Library
Determination of Neptunium in High Activity Waste (open access)

Determination of Neptunium in High Activity Waste

Technical report. From Abstract : "An existing ion exchange method was adapted for use in a shielded facility to separate Np237 from highly radioactive solutions. The subsequent determination of neptunium was made by alpha counting and alpha pulse height analysis. The coefficient of variation was $.8% (n=10) for a synthetic sample and 5.9% (n=23) for plant samples."
Date: September 1962
Creator: Holcomb, H. Perry
System: The UNT Digital Library
Radioactivity in the Environs of the Savannah River Plant January to July - 1954. (open access)

Radioactivity in the Environs of the Savannah River Plant January to July - 1954.

From abstract: "There were significant increases in radioactivity in the environs of the Savanna River Plant during the period from January 1954 to July 1954. All of these increases were relatively small as compared to the maximum permissible concentration. Although fallout from Pacific tests was the main contributor to the increased activity, some of the increase was due to normal Plant operations."
Date: November 1954
Creator: Horton, J. H., (J. Henry)
System: The UNT Digital Library
Isotopic Purification of Tritium by Electrolysis (open access)

Isotopic Purification of Tritium by Electrolysis

From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."
Date: May 1958
Creator: Johnson, B. S., Jr.; Grace, J. T.; Meyer, L. H.; Karraker, D. G. & Nicholson, C. K.
System: The UNT Digital Library
Ultrasonic Energy Applied to Aluminum Extrusion Cladding of Tubes (open access)

Ultrasonic Energy Applied to Aluminum Extrusion Cladding of Tubes

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 of the extrusion curves were altered. The effect appeared to be attributable to a reduction of both die friction and container wall friction under ultrasonic influence."
Date: November 1959
Creator: Jones, J. Byron; DePrisco, Carmine F.; Maropis, Nicholas & Thomas, John G.
System: The UNT Digital Library
A Monitor for Surface Adsorbed Tritium (open access)

A Monitor for Surface Adsorbed Tritium

From abstract: "A monitor for detection of surface-adsorbed tritium beta particles has been developed. The detecting element is a windowless Geiger tube with the counting gas flowing through it. The normal limit of detection of a single-tube probe is 800 d/m of tritium, while a three-tube probe is probably limited to about 2000 d/m. Both probes have a counting efficiency of about 10% for tritium."
Date: December 1953
Creator: Karraker, D. G.
System: The UNT Digital Library
Adsorption of Zirconium-Niobium on Silica Gel (open access)

Adsorption of Zirconium-Niobium on Silica Gel

From abstract: "Adsorption of radioactive zirconium-niobium from uranyl nitrate solutions by silica gel was increased by increasing the temperature and time the solution contacts silica gel, and decreased by "aging" the solutions before contacting the silica gel."
Date: July 1957
Creator: Karraker, David G. & Parker, Sidney G.
System: The UNT Digital Library
Fabrication of UO2 Fuel Elements by Vibrational Compaction (open access)

Fabrication of UO2 Fuel Elements by Vibrational Compaction

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, vibrational compaction procedure, sheath thickness, and fuel element shape on the maximum obtainable density were investigated."
Date: February 1962
Creator: Marah, Harold G.
System: The UNT Digital Library
Coextrusion of Powder-Compact Slugs (open access)

Coextrusion of Powder-Compact Slugs

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.
System: The UNT Digital Library
Irradiation of Thorium Slugs (open access)

Irradiation of Thorium Slugs

From abstract: "Ninety-two thorium slugs were irradiated in the Hanford piles to study the dimensional stability of the metal. The burnups that were incurred covered the range from 300 to 2800 ppm of the Th232. Slugs with burnups as high as 800 ppm were examined for visual and dimensional changes. The dimensional stability of these slugs was excellent, and no significant corrosion occurred on the aluminum cans. A cursory examination of slugs with burnups of greater than 800 ppm showed no gross dimensional instability."
Date: May 1956
Creator: Marshall, Robert P.
System: The UNT Digital Library
Ion-Chamber Water Monitor (open access)

Ion-Chamber Water Monitor

From abstract: "An instrument capable of detecting fission-product contamination in the moderator has been developed. It consists of a thin-walled ion chamber and associated electronic equipment for automatically detecting deviations from normal moderator decay rate. Indication of fission-product activity is independent of power level, flowrate, and other ambient conditions. Tests show the sensitivity and long-term stability to be good."
Date: February 1955
Creator: McCarthy, R. L.
System: The UNT Digital Library