Metallurgy Research Operation: Quarterly Progress Report, January - March 1965 (open access)

Metallurgy Research Operation: Quarterly Progress Report, January - March 1965

Quarterly progress report on a project to test the radiation effects on metallurgy.
Date: April 15, 1965
Creator: Cadwell, J. J.; Bierlein, T. K.; Bement, A. L.; Dillon, R. L. & Wheeler, R. G.
System: The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water (open access)

A Sequence for Predicting Waste Transport by Ground Water

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
System: The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1 (open access)

Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1

Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
System: The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2 (open access)

Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2

From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
System: The UNT Digital Library
Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand (open access)

Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand

Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."
Date: September 15, 1950
Creator: Calkins, G. D. & Filbert, R. B., Jr.
System: The UNT Digital Library
Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Abstract: "The effects of acidity on extraction of vanadium and molybdenum by diethyl ether are described. Solubility data for several vanadium compounds in nitrate process solutions are presented. Preliminary results on the extraction of uranium from process slurries by tributyl phosphate are reported, including data on the contaminants extracted with the uranium."
Date: November 15, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Topical Report on Chemical Process to Recover Uranium from Phosphate Rock (open access)

Topical Report on Chemical Process to Recover Uranium from Phosphate Rock

The following report summarizes research done on dissolving uranium from phosphate rock and superphosphate and recovering it from solution in a more concentrated form.
Date: November 15, 1947
Creator: Igelsrud, Iver
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

Abstract: "Dissolution of carnotite in several readily liquefiable gases, including ammonia, sulfur dioxide, chlorine, and nitrogen dioxide, was found to be negligible, even in the presence of uranium complexing agents. No low-boiling liquids have been found which will dissolve carnotite directly. Treatment with various sulfur chloride will convert carnotite to a form soluble in water or in certain organic solvents. Also, carnotite can be readily dissolved in HCl-acidified ethanol, methanol, or acetone. Amenability tests on nine western ores with HCl-methanol solvent indicated that uranium extractions greater than 90 per cent could be obtained if sufficient acid was used to insure some free acidity in the pregnant liquor. Temple Mountain and Sinbad-Muddy River ores were exceptions to this, uranium extractions being only about 50-60 per cent. Vanadium extractions were invariably lower than uranium extractions. Chemical analyses are presented for nine western ores."
Date: January 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System: The UNT Digital Library
The Determination of Rare Earths in Thorium (open access)

The Determination of Rare Earths in Thorium

Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
Date: May 15, 1952
Creator: Center, E. J.; Henry, W. M. & Householder, R. D.
System: The UNT Digital Library
The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report (open access)

The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
System: The UNT Digital Library
Zirconium Research and Development : Progress Report (open access)

Zirconium Research and Development : Progress Report

From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date: October 15, 1950
Creator: Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
System: The UNT Digital Library
Tungsten-Arc Welding of Ames Thorium and Thorium Alloys (open access)

Tungsten-Arc Welding of Ames Thorium and Thorium Alloys

This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
Date: January 15, 1952
Creator: Monroe, Robert E.; Martin, D. C. & Voldrich, C. B.
System: The UNT Digital Library
An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders (open access)

An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders

From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date: August 15, 1952
Creator: Harman, Cameron G.; Shinn, J., Jr. & Wagner, H. E.
System: The UNT Digital Library
Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report (open access)

Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date: May 15, 1953
Creator: Schwartz, C. M. & Vaughan, D. A.
System: The UNT Digital Library
Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report (open access)

Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report

Introduction: Among the many corrosion problems encountered in the production of uranium tetrafluoride and uranium metal from ores and concentrates, some of the most serious occur where hydrofluoric acid must be handled.
Date: June 15, 1953
Creator: Pray, H. A.; Fink, F. W.; Friedl, B. E. & Braun, W. J.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing non-aqueous extraction methods for leaching Western ores of uranium and vanadium.
Date: April 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

The following progress report is part of a series of reports on the study of nonaqueous extractive methods for western uranium ores. This report continues studies on HCl-methanol leaching of Western ores, primarily on Temple Mountain ores.
Date: July 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System: The UNT Digital Library
An Experimental Survey of the Heat-Treatment Response of some Zirconium-Uranium Alloys (open access)

An Experimental Survey of the Heat-Treatment Response of some Zirconium-Uranium Alloys

Abstract: "The heat-treatment behavior of zirconium alloys containing 7 to 70 w/o uranium is described. The effect of oxygen contamination on the structure and hardness of these alloys is outlined. It is shown that in the initial stages pf transformation of beta zirconium-uranium solid solution into the low-temperature phases a potent hardening reaction occurs in alloys containing 20 to 70 w/o uranium. In this reaction the hardness may rise from 200 DPH characteristic of retained beta to values in excess of 400 DPH. Practical heat treatments have been developed which produce relatively soft alloys. The microstructures and hardnesses produces by these treatments are shown."
Date: June 15, 1956
Creator: Saller, Henry A.; Rough, Frank A. & Chubb, Walston
System: The UNT Digital Library
Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops (open access)

Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops

From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."
Date: September 15, 1953
Creator: Stang, J. H.; Lagedrost, J. F.; Simons, E. M. & Dayton, R. W.
System: The UNT Digital Library
Evaluation and Consolidation of Electrolytic Thorium (open access)

Evaluation and Consolidation of Electrolytic Thorium

Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date: June 15, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
System: The UNT Digital Library
The Kinetics of the Zirconium-Uranium Dioxide Reaction (open access)

The Kinetics of the Zirconium-Uranium Dioxide Reaction

This report discusses three experimental methods used to study the kinetics of the reaction between zirconium and UO2.
Date: August 15, 1955
Creator: Mallett, Manley William, 1909-; Gerds, Arnold F.; Lemmon, Alexis W. & Chase, Dan L.
System: The UNT Digital Library
Critical-Assembly Studies on an Intermediate Reactor for Aircraft Propulsion (open access)

Critical-Assembly Studies on an Intermediate Reactor for Aircraft Propulsion

The following report studies an intermediate solid-fuel reactor system for aircraft propulsion.
Date: July 15, 1957
Creator: Marinaccio, Lawrence F.; Jung, Richard G.; Jankowski, Francis J.; Dingee, David A. & Chastain, Joel W.
System: The UNT Digital Library