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
Topical report on examination of residues from the nitric acid digestion of pitchblende (open access)

Topical report on examination of residues from the nitric acid digestion of pitchblende

A report about an investigation started to determine the compounds and/or minerals present in the residue resulting from nitric acid digestion of ore. Emphasis was placed on determining the compounds and/or minerals containing boron.
Date: 1950
Creator: Langston, B.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Beta-Counting Methods Applied to the Determination of Uranium in Low-Grade Ores (open access)

Beta-Counting Methods Applied to the Determination of Uranium in Low-Grade Ores

The following report covers investigations on the application of the beta counter as an analytical tool for use in experiments on the extraction and concentration of uranium from low-grade (.005-.02 % uranium) shale and phosphate rock ores.
Date: July 1947
Creator: Doig, J. R.; Igelsrud, Iver; Nelson, H. R. & Schwartz, C. M.
System: The UNT Digital Library
Welding of High-Strength Stainless Steels for Pressure Vessels (open access)

Welding of High-Strength Stainless Steels for Pressure Vessels

The following report describes the welding characteristics of several high-strength stainless steels that were considered for use as a pressure vessel to operate at high pressures at 800 F.
Date: April 5, 1954
Creator: Vagi, J. J.; Thompson, V. R. & Martin, D. C.
System: The UNT Digital Library
Electroplated Metals on Uranium (open access)

Electroplated Metals on Uranium

The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.
Date: May 7, 1954
Creator: Beach, John G.; Schickner, W. C.; Konecny, C. R. & Faust, Charles L.
System: The UNT Digital Library
Temperature distributions in a reactor fuel plate (open access)

Temperature distributions in a reactor fuel plate

A report about a method for fabricating 30-in long stainless steel UO2 fuel sheet and the properties of the fabricated sheet were investigated.
Date: 1954
Creator: Chastain, Joel W.; Fawcett, Sherwood L.; Jung, R. G.; Long, J. K. & Redmond, R. F.
System: The UNT Digital Library
The Fabrication of Subassemblies for the Supercritical-Water Reactor (open access)

The Fabrication of Subassemblies for the Supercritical-Water Reactor

In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
System: The UNT Digital Library
Nondestructive Measurements of Aluminum and Nickel Layers on Uranium (open access)

Nondestructive Measurements of Aluminum and Nickel Layers on Uranium

From introduction: "This report covers the development of nondestructive techniques for measuring quantitatively: (1) thickness of electrodeposited-nickel diffusion barriers, and (2) thickness of aluminum cladding on flat-plate fuel elements."
Date: June 12, 1954
Creator: Glaze, E. W.; Rhoten, M. L.; Kulp, B. A.; Cooley, K. D. & Wenk, S. A.
System: The UNT Digital Library
Corrosion of Type 347 Stainless Steel in the Uranium-Derby Pickle Bath (open access)

Corrosion of Type 347 Stainless Steel in the Uranium-Derby Pickle Bath

Abstract: In one of the final stages of the process at the Mallinckrodt Uranium Refining Center, a 45 per cent nitric acid solution at about 170 F is used to pickle the calcined magnesium fluoride scale off the uranium derbies. The increase in the fluoride-ion content of the bath tends to promote corrosion of the Type 347 stainless tanks. This attack becomes excessive if 0.3 g/liter of fluoride ion or more is present. It was found that if aluminum ion is added to the solution the corrosiveness of the bath can be controlled. Two or three times as much aluminum ion as fluoride ion present is found satisfactory at 170 F. Indications are that the tying up of the fluoride-ion by the complexion [AlF6]8 is responsible for the corrosion control.
Date: July 14, 1954
Creator: Peoples, R. S.; Fink, F. W.; Stewart, O. M. & Braun, W. J.
System: The UNT Digital Library
Evaluation of Methods of Brazing Aluminum Spacing Fins to Flat-Plate Aluminum-Clad Fuel Elements (open access)

Evaluation of Methods of Brazing Aluminum Spacing Fins to Flat-Plate Aluminum-Clad Fuel Elements

Abstract: "Four brazing methods and one other joining process were evaluated for the joining of aluminum spacer fins to flat-plate aluminum-clad fuel elements. None of these methods appear completely suitable for use in a mass-production operation. Furnace brazing and salt-bath brazing were most promising. However, the mechanical problems involved in the application of either process deter their recommendation. Resistance brazing and torch-brazing were proven impractical. The great difference in mass between the two pieces being joined prevents the use of either the resistance or torch method. Pressure bonding is not applicable because of the excessive deformation of parts being joined."
Date: July 23, 1954
Creator: Evans, R. M. & Martin, D. C.
System: The UNT Digital Library
Thermodynamic evaluation of materials in contact with fluoride fuels (open access)

Thermodynamic evaluation of materials in contact with fluoride fuels

A report about the corrosion tendencies of 64 metallic elements, nonmetallic elements, and carbides evaluated by means of thermodynamic methods.
Date: 1954
Creator: Crooks, R. C.; Sparrow, D. E.; Ward, J. J. & Filbert, Robert B., Jr.
System: The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod (open access)

The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
System: The UNT Digital Library
The tensile strength of solid-state bonded aluminum and nickel-plated uranium (open access)

The tensile strength of solid-state bonded aluminum and nickel-plated uranium

A report intended to aid in the evaluation of solid-state bonding techniques for cladding natural-uranium fuel-element cores with aluminum, tensile specimens which are 1/4 in. in diameter and 3 in. long.
Date: 1954
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
System: The UNT Digital Library
Development of Methods for End Capping PWR Fuel Elements (open access)

Development of Methods for End Capping PWR Fuel Elements

The following report discusses the development of methods for sealing the ends of metallic-cored fuel rods.
Date: December 28, 1955
Creator: Vagi, J. J. & Martin, D. C.
System: The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod (open access)

The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Abstract: "The effects of nitrogen, slag, and hydrogen additions on the surface quality of rolled uranium rod were studied. The addition of 400 ppm of nitrogen resulted in severe striations. Slag inclusions elongated during rolling and produced short open seams in the etched surface. The effects of 9 to 10 ppm of hydrogen were obscured by defects in the original costings. These defects were caused by oxide films entrapped in the ingot."
Date: 1956
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
System: The UNT Digital Library
Investigation of Methods for End Capping Stainless Steel Pins (open access)

Investigation of Methods for End Capping Stainless Steel Pins

This report follows investigations of methods for sealing the ends of stainless steel-uranium oxide fuel pins with the objective to develop an end-capping method that would give consistently good-quality closures in production.
Date: May 18, 1956
Creator: Vagi, Julius J.; Thompson, Harold B. & Martin, David C.
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 Ammonium Uranates (open access)

Investigation of Ammonium Uranates

This report studies ammonium dichromate and the conditions it needs to be under in order to precipitate and be isolated from an aqueous system.
Date: July 19, 1956
Creator: Ewing, Robert A.; Kiehl, Samuel J. & Bearse, Arthur E.
System: The UNT Digital Library
Degradation Products of Tributyl Phosphate (open access)

Degradation Products of Tributyl Phosphate

Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents were found in plant solvents. Diluent degradation is postulated as the source of these components. Emulsion-formation tendencies appeared to correlate better with concentrations of these contaminants than with dibutyl phosphate content."
Date: February 17, 1956
Creator: Ewing, Robert A.; Kiehl, Samuel J. & Bearse, Arthur E.
System: The UNT Digital Library
The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys (open access)

The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys

Abstract: "The corrosion rate in 680 F water of the uranium-50 w/o zirconium binary alloy was found to be -0.20 mg/(cm2)(hr), and that of the uranium-40 w/o zirconium binary alloy was -0.34 mg/(cm2)(hr). Both alloys correlated uniformly, with no evidence of discontinuous failure. Normal variations in interstitial content in either alloy had no significant effect on corrosion behavior. Tantalum additions, in the range of 0.2 to 5 w/o, improved the corrosion rate of the uranium-50 w/o zirconium base, with a minimum rate of -0.06 mg/(cm2)(hr) for the 5 w/o tantalum alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy decreased the corrosion rate of the base to -0.11 mg/(cm2)(hr) in the [...] condition only. In either conditions, the 5 w/o tantalum alloy failed discontinuously. All other additions to both bases either had no effect or decreased corrosion resistance. These included aluminum, chromium, iron, molybdenum, nickel, platinum, tin, titanium, tungsten, and vanadium additions."
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E., 1922-; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert Isaac, 1917-
System: The UNT Digital Library
Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures (open access)

Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures

Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mistakes of UF4 containing from 10 to 40 w/o UO2."
Date: June 28, 1956
Creator: Ewing, Robert A. & Bearse, Arthur E.
System: The UNT Digital Library
Effect of Ceramic or Metal Additives in High-UO₂ Bodies (open access)

Effect of Ceramic or Metal Additives in High-UO₂ Bodies

The following report focuses on research made to determine whether the service performance of UO₂ fuel-elements cores for the PWR can be improved by certain ceramic or metal additions.
Date: July 24, 1956
Creator: Bowers, Donald J.; Hedden, Walter A.; Snyder, M. Jack & Duckworth, Winston H.
System: The UNT Digital Library
Corrosion of Uranium Alloys in High-Temperature Water (open access)

Corrosion of Uranium Alloys in High-Temperature Water

This report is one of a series of five, dealing with alloys of the uranium-zirconium series. Particularly, this report focuses on the corrosion properties of uranium alloys, with zirconium as the major alloying agent, in high-temperature water.
Date: 1953
Creator: Pray, H. A. & Berry, Warren E., 1922-
System: The UNT Digital Library
Welded Closures for Fuel Elements (open access)

Welded Closures for Fuel Elements

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."
Date: October 8, 1953
Creator: Sopher, R. P.; Martin, G. E.; Grable, G. B.; Voldrich, C. B.; Leatherman, A. F. & Todd, F. C.
System: The UNT Digital Library