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Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960 (open access)

Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960

Programming research in the construction of a translator to Oracle language from ALGOL.
Date: April 6, 1961
Creator: unknown
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: April 6, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures (open access)

Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures

Investigation of the flow through straight-through , elbow, and tee "AN" fittings at negligible approach velocity with approach temperatures up to 1100 degrees F.
Date: March 6, 1957
Creator: Ducoffe, Arnold L.; Bennett, John R. & Ray, C. Gable
System: The UNT Digital Library
The Crystal Structure of Uranium Tetrafluoride (open access)

The Crystal Structure of Uranium Tetrafluoride

Fourier refinement analysis of the uranium parameters in uranium tetrafluoride.
Date: June 6, 1951
Creator: Burbank, R. D.
System: The UNT Digital Library
Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils (open access)

Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils

Results of experimental investigation for improving intensification and to reduce stress concentrations for anvil redesign.
Date: December 6, 1963
Creator: Huddleston, R. L.
System: The UNT Digital Library
SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960 (open access)

SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960

From introduction: "The contract covers final design of the SM-2 Nuclear Power (PWR) Steam Electric Station, described in the preliminary design report, APAE 40, Volumes I and II."
Date: April 6, 1960
Creator: Knighton, G. W.
System: The UNT Digital Library
Geological Investigation of the Trachyte District, Henry Mountains, Utah (open access)

Geological Investigation of the Trachyte District, Henry Mountains, Utah

Abstract: Uranium-vanadium ore has long been known in the Trachyte district. Production started in 1913 and has been erratic and intermittent to date. Until recently, practically all production from the Henry Mountains area has come from the Trachyte district.
Date: December 6, 1951
Creator: Brooke, Gerald L.; Shirley, Raymond F. & Swanson, Melvin A.
System: The UNT Digital Library
Cyclotron Component Design Technical Reports (open access)

Cyclotron Component Design Technical Reports

From introduction: The study of cyclotron-magnet design presented here is directed toward attaining a large ratio of energy in the ion beam with respect to cost. Alternatively, the goal may be regarded as a smaller, more convenient apparatus. These two objectives are not completely incompatible; a design that is more economical than the usual is also smaller. The best design of a cyclotron can be obtained only by considering the problem as a whole. The conditions necessary to maintain an ion beam, the conditions required for the operation of the oscillator, and a host of other problems influence the design of the magnet. It is assumed in this paper that the "other problems" can be satisfactorily solved, if the gap has a suitable geometry and the field a suitable space dependence.
Date: February 6, 1952
Creator: Foss, M. H.
System: The UNT Digital Library
The Distribution of Calcretes and Gypcretes in Southwestern United States and Their Uranium Favorability: Based on a Study of Deposits in Western Australia and South West Africa (Namibia) (open access)

The Distribution of Calcretes and Gypcretes in Southwestern United States and Their Uranium Favorability: Based on a Study of Deposits in Western Australia and South West Africa (Namibia)

From summary: The procedure has been to search for areas in which nonpedogenic calcrete or gypcrete may have developed and where additional study or exploration might be justified.
Date: January 6, 1978
Creator: Carlisle, Donald
System: The UNT Digital Library
Computed Values of X-Ray Lines and Limits for the Trans-Uranic Elements (open access)

Computed Values of X-Ray Lines and Limits for the Trans-Uranic Elements

Report detailing values of x-ray lives and limits for trans-uranic elements. Formulas and methods are detailed throughout the report.
Date: September 6, 1944
Creator: Monk, Ardis T. & Allison, Samuel King
System: The UNT Digital Library
Recovery From Salvage Residue by Fluorination in Vertical Reactors (open access)

Recovery From Salvage Residue by Fluorination in Vertical Reactors

Report discussing trial runs of a method of recovery of uranium from salvage residue. The method involves hydrofluorination of the residue to remove large quantities of interfering silicates, followed by a fluorination treatment to remove uranium.
Date: September 6, 1946
Creator: Stevenson, K., Jr.; Blasewitz, A. G. & Clewett, G. H.
System: The UNT Digital Library
Separation of Tuballoy From Tantalum by Chlorination Distillation Process (open access)

Separation of Tuballoy From Tantalum by Chlorination Distillation Process

Abstract: Tuballoy can be effectively separated from tantalum filaments by chlorination of the filaments and subsequent distillation and condensation of tantalum chloride. Apparatus for chlorination of filaments and distillation separation in one unit is under consideration. Chemical methods of separation of tuballoy from distillation residues are being tested.
Date: February 6, 1946
Creator: Adams, R. H.; Rogers, J. A.; Wagner, E. L. & Miller, A. J.
System: The UNT Digital Library
Progress Report on Carnotite Studies; Carbonate Processes: September 1949 (open access)

Progress Report on Carnotite Studies; Carbonate Processes: September 1949

This is a progress report on the carbonate process, compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, covering the month of September, 1949. In the previous month, the problem of immediate interest to the Monticello operation were listed. Projects that were left incomplete during that time were continued during this month, as well as a brief investigation of the process in which raw ore is leached with sodium carbonate, the sands and slime separated, the sands leached with acid, and the slimes roasted in a pellitized form.
Date: October 6, 1949
Creator: Brown, K. B. & Coleman, C. F.
System: The UNT Digital Library
Capture Cross Section of Si for Thermal Neutrons (open access)

Capture Cross Section of Si for Thermal Neutrons

The following report analyzes different values and measurements that give the same results for the captured cross section of thermal neutrons for Si.
Date: May 6, 1942
Creator: Coon, J. H.
System: The UNT Digital Library
Oriented Dioxide Films on Uranium (open access)

Oriented Dioxide Films on Uranium

This report deals with the formation of oriented layers of an oxide which form during oxidation without any evident relationship to the parent and underlying metal. It is offered without explanation or proposed mechanism.
Date: July 6, 1954
Creator: Waber, James T. & O'Rourke, J. A.
System: The UNT Digital Library
Preparation of Some Protactinium Compounds and the Metal (open access)

Preparation of Some Protactinium Compounds and the Metal

Report discussing methods for preparing various protactinium compounds, including protactinium oxides, tetrafluoride, and oxysulfide. Additionally, a method for making the protactinium metal is mentioned.
Date: April 6, 1951
Creator: Sellers, Philip A.; Fried, Sherman; Elson, Robert E. & Zachariasen, William H.
System: The UNT Digital Library
The Diffusion Length and the Utilization of Thermal Neutrons in a Heterogeneous Pile (open access)

The Diffusion Length and the Utilization of Thermal Neutrons in a Heterogeneous Pile

Abstract: "An accurate calculation is given for the quantity which corresponds to the diffusion length in the theory of the pile. The procedure is to establish a relationship between the diffusion length and the change in thermal utilization from a pile with infinite sides to one with sides of a finite length. The calculation of this change in the thermal utilization is then carried through. Approximation to the answer and numerically exact calculations are given in the report. The results show that for radif very near the optimum values the exact diffusion length is slightly larger than the one obtained from the usual formula...However, over most of the range of radii the exact diffusion length is smaller than the approximate one."
Date: October 6, 1943
Creator: Plass, Gilbert N.
System: The UNT Digital Library
Recovery of Zirconium Tetrachloride Powder (open access)

Recovery of Zirconium Tetrachloride Powder

Report discussing methods for recovering hafnium-free zirconium from irradiated fuel elements. Two methods are discussed: the fluoride method and the Zircex method. Experimental procedures to evaluate these methods and their results are presented.
Date: April 6, 1956
Creator: Lee, L. A. & Welt, M. A.
System: The UNT Digital Library
Suggested Correction to Age-Diffusion Equation as Used by the ANP Physics Group (open access)

Suggested Correction to Age-Diffusion Equation as Used by the ANP Physics Group

Report presenting a correction to an age-diffusion equation used by ANP Physics Group, as well as a test calculation using the corrected equation.
Date: November 6, 1951
Creator: Coveyou, R. R. & Macauley, B. T.
System: The UNT Digital Library
Materials Handbook : Part V - Properties of Thorium (open access)

Materials Handbook : Part V - Properties of Thorium

"These notes are intended to serve as a summary of the current knowledge of properties of materials. In the future some need may exist for related information on methods od testing, design and fabrication. This issue presents information on thorium with subdivisions..."
Date: May 6, 1953
Creator: Wendell, George E.; Majors, Harry, Jr.; Wallace, R. H. & Webster, R. T.
System: The UNT Digital Library
Specification for Cleaning Zircaloy Fuel Rod Components (open access)

Specification for Cleaning Zircaloy Fuel Rod Components

Abstract: "This specification covers the cleaning of Zir caloy-2 components of PWR fuel rods and such tools, gauges, or other devices as may be required in subsequent handling, welding and inspection per Fuel Rod Specification AP-292545, Section II-A-4 and Section II-B-3."
Date: March 6, 1956
Creator: Fischer, R. L.
System: The UNT Digital Library
Factors Affecting the Precipitation of Tubanyl Peroxide from Gunk Solutions at Reduced Temperatures (open access)

Factors Affecting the Precipitation of Tubanyl Peroxide from Gunk Solutions at Reduced Temperatures

The following report presents data from the investigations on discovering factors affecting the precipitation of tubanyl peroxide from Alpha and Beta gunk solutions at reduced temperatures.
Date: March 6, 1945
Creator: Brown, K. B.; Swanson, D. M.; Wagner, E. L. & Miller, A. J.
System: The UNT Digital Library
Mass Spectrometric Determination of Isotopic Ratio with Varying Ion Beam Intensity (open access)

Mass Spectrometric Determination of Isotopic Ratio with Varying Ion Beam Intensity

Summary: "An apparatus is described which applies alternate pulses from two ion beams to a galvanometer network. The isotopic ratio is read directly from a potentiometer. The comparison is independent of ion beam intensity. This method is not practical for application to the standard Nier assay instrument because of the low ion currents normally used. It is suggested that this comparison method may have utility in a spectrometer utilizing a high intensity ion source such as capillary ore or condensed spark."
Date: March 6, 1946
Creator: Cameron, Alan E. & White, J. R.
System: The UNT Digital Library
Reclamation of Contaminated Diffusion Pump Oil and Removal of Tuballoy Therefrom (open access)

Reclamation of Contaminated Diffusion Pump Oil and Removal of Tuballoy Therefrom

Abstract: The possibilities for the removal of tuballoy from diffusion pump oil and reclamation of the oils for reuse are discussed. The report includes specifications of practical equipment, operating instructions, photographs and diagrams of the necessary construction details.
Date: December 6, 1945
Creator: Lee, J. E. Jr. & Susano, C. D.
System: The UNT Digital Library