Preliminary Studies of the Adsorption of Uranium in a Resin-In-Pulp System (open access)

Preliminary Studies of the Adsorption of Uranium in a Resin-In-Pulp System

Data were obtained in non-flowing and flowing (continuous) batch adsorption systems to serve as a guide to the operating conditions that should be used in a resin-in-pulp adsorption system for the recovery of uranium from ores.
Date: July 27, 1953
Creator: Abrams, Charles S. & Kaufman, David
System: The UNT Digital Library
Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores (open access)

Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores

In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.
Date: March 2, 1953
Creator: Abrams, Charles S.; Moulton, Harry D. & Viklund, Hans I.
System: The UNT Digital Library
Graphitization Processes in Cokes and Carbon Blacks (open access)

Graphitization Processes in Cokes and Carbon Blacks

Abstract: "The effect of heat treatment of 2000 to 4650 F on the structure of carbons from several sources have been investigated, using X-ray diffraction. Of particular interest was the effect of temperature on the degree of graphitization. The process of graphitization results in a larger graphite crystallite size in the ao direction, the plane of the layers, than in the co direction. No correlation was found between the structure of the coke heated at 2000 F and the degree of graphitization attained at 4650 F. Materials coked in a closed retort yielded a more perfect graphite structure than the same material coked with access to air. Carbon blacks yield graphite with a greater co lattice constant than cokes with comparable crystallite sizes."
Date: June 19, 1953
Creator: Austin, A. E. & Hedden, W. A.
System: The UNT Digital Library
The Chemistry of Uranium(VI) Orthophosphate Solutions (open access)

The Chemistry of Uranium(VI) Orthophosphate Solutions

From introduction: This is the first in a series of reports describing an investigation of the chemistry of uranium(VI) orthophosphate solutions which is at present underway in this laboratory. Spectrophotometric, potentiometric and solubility studies have been carried out, and it is the first of these which is reported here.
Date: June 22, 1953
Creator: Baes, Charles F., Jr.; Schreyer, J. M. & Lesser, J. M.
System: The UNT Digital Library
Experimental Simulation of Plateau Type Uranium Deposits (open access)

Experimental Simulation of Plateau Type Uranium Deposits

From abstract: Experimental simulation of Colorado Plateau type uranium deposits is divided into seven parts. The first three summarize the essential features of geological occurrence for the ores. The last four parts outline the results of experimental investigation arranged according to each geological group of features influencing mode of occurrence.
Date: January 1953
Creator: Bain, George W.
System: The UNT Digital Library
Cross Section for the Formation of Be⁷ from Oxygen Irradiated with High Energy Deuterons (open access)

Cross Section for the Formation of Be⁷ from Oxygen Irradiated with High Energy Deuterons

Abstract: "The cross section for the formation of Be⁷ from oxygen irradiated with high energy deuterons has been determined. The values are 4.5 millibarns at 100 Mev, 5.6 millibarns at 150 Mev, and 5.5 millibarns at 190 Mev."
Date: September 1953
Creator: Batzel, Roger Elwood & Coleman, G. H.
System: The UNT Digital Library
Performance of the Disassembly Equipment : NYX Test No. 2.9.1, 2.9.3 (open access)

Performance of the Disassembly Equipment : NYX Test No. 2.9.1, 2.9.3

Abstract: "The NYX testing of the component disassembly equipment comprised repeated operation of both the quatrefoil disassembly machine and the foil press and shear to evaluate the suitability of these machines to perform their design function with reliability and convenience of operation. During testing, both design and operational deficiencies were found and corrected in the NYX equipment. In general, both machines operated satisfactorily after modification."
Date: February 1953
Creator: Bernath, Louis & Thompson, J. N., Jr.
System: The UNT Digital Library
Hydrolysis of Uranium Tetra-Fluoride (open access)

Hydrolysis of Uranium Tetra-Fluoride

The following report provides tables that measure the pressure of hydrogen fluoride at given temperatures and the hydrolysis of uranium tetrafluoride.
Date: January 10, 1953
Creator: Bernhardt, Harvey A.
System: The UNT Digital Library
Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1 (suppl.) (open access)

Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1 (suppl.)

Supplement to Progress Report on Flotation of Uranium Bearing Materials From Lake Athabaska Ore, Sample 43-1 that includes information on uranium lost in solution during flotation in an acid circuit.
Date: December 28, 1953
Creator: Breymann, John B.
System: The UNT Digital Library
Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1 (open access)

Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1

At the request of the Atomic Energy Commission, a 456 pound sample of Lake Athabaska ore was shipped to this laboratory by the Radioactivity Division of the Canadian Bureau of Mines. The sample was received on March 10, 1952 and given our number 43-1. Several series of flotation tests were performed on the sample.
Date: October 12, 1953
Creator: Breymann, John B.; Charles, W. D. & Thomas, P. N.
System: The UNT Digital Library
Technical Progress Report for the Period July 16 through August 15, 1953 (open access)

Technical Progress Report for the Period July 16 through August 15, 1953

A report about copper-based cladding alloys and the alloying reactions based on these metals. Experiments are done to minimize the risk of melting extrusion billets.
Date: 1953
Creator: Bridgeport Brass Company
System: The UNT Digital Library
Corrosion of Aluminum and Beryllium by MTR Canal Water (open access)

Corrosion of Aluminum and Beryllium by MTR Canal Water

Introduction: "In the early operation of the WTR severe canal corrosion of dummy fuel assemblies and a beryllium A-piece caused a great deal of concern as to the possible effects of long-time canal storage on such elements. A short-term experimental program was started to determine the causes of this corrosion and to correct them before any irradiated fuel elements had to be stored in the canal. The results of this program are presented here."
Date: January 14, 1953
Creator: Burnham, J. B., Jr. & Bartz, M. H.
System: The UNT Digital Library
Attritioning of Temple Mountain Ore (open access)

Attritioning of Temple Mountain Ore

Abstract: The results of both dry and wet attritioning of Temple Mountain ore are presented. In order to obtain effective attritioning on this ore, the amphaltite must be removed before attritioning. With the asphaltite present, dry attritioning causes a build-up of asphaltite on the surface of sand grains, with consequent loss of uranium values. In wet attritioning, the asphaltite is not broken down or attritioned, because of its low specific gravity and resilience.
Date: June 19, 1953
Creator: Butler, J. N.; Stephens, R. W. & Ehrlinger, H. P., III
System: The UNT Digital Library
Technical Data Book, Feed Materials Production Center, Fernald, Ohio: Part 22 (open access)

Technical Data Book, Feed Materials Production Center, Fernald, Ohio: Part 22

The Technical Data Book compiles useful chemical and physical data of feed materials, chemicals, uranium intermediates and end products of the FMPC, Fernald, Ohio. The data presented encompass the process operations involved in the original integrated FMPC project, the uranium hexafluoride reduction plant and the throium plant.
Date: February 24, 1953
Creator: Catalytic Construction Company. Process Engineering Staff.
System: The UNT Digital Library
An Experimental Method to Determine Equation of State Data for Solids by Shock Wave Measurements (open access)

An Experimental Method to Determine Equation of State Data for Solids by Shock Wave Measurements

The following report describes and experimental method used to determine equation of state of materials under strong shock. The method was devised of simultaneously measuring the velocity of the shock through a plate, and the velocity of the free surface after the shock has traversed the plate. Further analysis is presented.
Date: 1953
Creator: Christian, Russell H. & Walsh, John M.
System: The UNT Digital Library
Uranium production : process designs for leached zone plants (open access)

Uranium production : process designs for leached zone plants

This volume in the thirteenth in a series of reports dealing with the recovery of uranium, alumina and phosphate values from the leached zone portion of the Florida phosphate producing area.
Date: September 1953
Creator: Clements, D. F.; McCullough, R. F.; Williams, W. G. & Wrege, E. E.
System: The UNT Digital Library
Influence of Absorption on the Effective Value of Eta (open access)

Influence of Absorption on the Effective Value of Eta

This report follows calculations performed to determine the effect of epithermal capture on the value of eta to be used in lattice calculations.
Date: January 22, 1953
Creator: Cohen, E. Richard, 1922-
System: The UNT Digital Library
The Furnace Spectrum of Plutonium (open access)

The Furnace Spectrum of Plutonium

Abstract: "The spectrum of plutonium has been observed over the temperature range of 2000 to 2600 C and a wavelength coverage of 3476 to 6888 A. The spectrum was excited in a modified King furnace."
Date: May 12, 1953
Creator: Conway, John G.
System: The UNT Digital Library
Liquid-Liquid Extraction (open access)

Liquid-Liquid Extraction

Abstract: "Extraction equipment of the multistage mixer-settler type has been found useful for providing the intensive contact between phases that is required in processes involving complex compounds of the heavy metals. In this report, the factors of mixer-settler design and operation are discussed with reference to the known types of mixer-settler units. Following this review, a detailed description is given of mixer-settler units constructed and installed in this laboratory."
Date: May 1953
Creator: Davis, Milton Wickers, Jr.; Hicks, Thomas E. & Vermeulen, Theodore
System: The UNT Digital Library
Coulometric Titration Plutonium (open access)

Coulometric Titration Plutonium

Abstract:"A method is described for the electroreduction of plutonium to the +3 valence state in a nitric acid-sulfamic acid solution. Exploratory experiments in the search for a coulometric titration of Pu(III) using electrolytically generated ceric ion are also described. The results strongly indicate that a convenient procedure can be devised. Suggestions for future work are presented."
Date: February 17, 1953
Creator: Dreeben, A. B.
System: The UNT Digital Library
Drilling at Seven Mile Canyon, Grand County, Utah (open access)

Drilling at Seven Mile Canyon, Grand County, Utah

Discussing uranium deposits drilled at the Seven Mile Canyon in grand county, Utah.
Date: January 12, 1953
Creator: Droullard, Robert F. & Farrow, Chester E.
System: The UNT Digital Library
Fracture Studies in the Lucero Uplift, New Mexico: Final Report (open access)

Fracture Studies in the Lucero Uplift, New Mexico: Final Report

Objectives: The purpose of this project was to study in detail the factors controlling the formation of fractures and the fracture pattern actually developed in an area transitional between Colorado Plateau and Basin and Range type structures.
Date: December 1953
Creator: Duschatko, Robert W.
System: The UNT Digital Library
Crystal Structure of a KPuO₂CO₃, NH₄ PuO₂CO₃, RbAmO₂CO₃ (open access)

Crystal Structure of a KPuO₂CO₃, NH₄ PuO₂CO₃, RbAmO₂CO₃

From abstract: "The preceding article describes the preparation of a number of alkali carbonates of pentavalent neptunium, plutonium, or americium. The results of x-ray diffraction studies of some of these carbonate precipitates are presented in the present paper. The preparations to be dealt with are the K-Pu(V) (at low pH), NH4-Pu(V) and Rb-Am(V) precipitates which form one iso-structural series. In the case of the other preparations discussed in the preceding article, the x-ray work did not lead to reliable conclusions as to chemical formula and crystal structure."
Date: 1953
Creator: Ellinger, F. H. & Zachariasen, William H.
System: The UNT Digital Library
The Kinetics of the Circulating-Fuel Nuclear Reactor (open access)

The Kinetics of the Circulating-Fuel Nuclear Reactor

Abstract: "In a circulating-fuel reactor, the circulation of the fuel cause a damping of power oscillations of the reactor. This is demonstrated under the assumption, that there is no mechanical vibration coupled with the oscillation of reactor power, and that the shapes of the hydrodynamic flow does not vary with time."
Date: March 30, 1953
Creator: Ergen, W. K.
System: The UNT Digital Library