Collection
Serial/Series Title
Country
23 Matching Results
Results open in a new window/tab.
Results:
1 - 23 of
23
The Roll Cladding of Uranium With Aluminum
Report discussing a study regarding rolling as a technique for making uranium fuel elements that are flat-plate and aluminum-clad.
Date:
August 3, 1954
Creator:
Saller, Henry A.; Paprocki, Stan J. & Delaney, J. F.
System:
The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
This report describes progress in testing nonaqueous methods for extracting uranium and vanadium from Western ores. Acetone leaches were found to be effective.
Date:
January 20, 1954
Creator:
Ewing, R. A.; Kiehl, S. J., Jr.; Kimball, R. B. & Bearse, A. E.
System:
The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
The following progress reports continues the investigation of the HCl-acetone process for extracting uranium, discovering that it is applicable to most Western ores, yielding high uranium recoveries. The economics of the process have been improved by substitution of sulfuric acid for part of the hydrochloric acid requirements.
Date:
April 20, 1954
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
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
This report describes progress regarding construction of a small pilot plant and a five-step process involving hydrochloric-sulfuric acid treatment and acetone extraction.
Date:
October 20, 1954
Creator:
Ewing, R. A.; Foley, D. D.; Filbert, Robert B., Jr. & Bearse, A. E.
System:
The UNT Digital Library
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
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
Properties of Stainless Steel-Uranium Dioxide Fuel Plates
From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."
Date:
May 11, 1954
Creator:
Keeler, J. R. & Cuddy, L. J.
System:
The UNT Digital Library
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
A Recirculating Supercritical Water Loop
From Abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date:
October 25, 1954
Creator:
Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
System:
The UNT Digital Library
A Recirculating Supercritical Water Loop
From abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date:
October 25, 1954
Creator:
Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
System:
The UNT Digital Library
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-UOâ‚‚ 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
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
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
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
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
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
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
The casting of radiator-type fuel elements of the uranium-chromium eutectic alloy
From abstract: "The feasibility of casting a bare, radiator-type fuel element of the uranium-chromium eutectic alloy (5 w/o chromium) was investigated."
Date:
1954
Creator:
Saller, Henry A.; Dickerson, R. F.; Hare, Alan W. & Murr, W. E.
System:
The UNT Digital Library
A study of the dip coating of uranium sheet with aluminum-silicon alloy
A report which covers an investigation of techniques for producing hot-dip Al-Si coatings on uranium sheet. Also, the study is concerned with the effects of time and temperature of dipping on the intermetallic zone and its ductility.
Date:
1954
Creator:
Cawthorne, E. W.; Craighead, C. M; Berry, Warren E., 1922-; Pray, H. A. & Jaffee, Robert Isaac, 1917-
System:
The UNT Digital Library
The strength of wrought zirconium-base binary alloys at 1800 to 2200 F
A report which investigated the effects of a number of elements on the workability, hardness, and high-temperature strength of zirconium were investigated.
Date:
1954
Creator:
Saller, Henry A.; Stacy, J. T. & Porembka, Stanley W.
System:
The UNT Digital Library
The Fabrication of Stainless Steel-Uranium Dioxide Fuel Elements
Abstract: "Stainless steel-clad fuel sheet 0.020 in. thick with a 0.008-in. core of stainless steel plus UO2 was produced by roll cladding a powder metal compact. The effects of processing variables, core-matrix composition, quantity of oxide, and oxide particle size on the properties of the sheet were investigated. The strength and ductility of the core decreased sharply as the quantity of oxide in the core increased from 20 to 40 w/o. Over the range of matrix compositions investigated the particle size of the oxide had little affect on the core strength. In cores containing 21 w/o of oxide. 18 w/o chromium, 82 w/o iron matrix prepared from the elemental metal powders had the highest strength and ductility, but this matrix was susceptible to cracking during thermal cycling. As elemental 18 w/o chromium, 9 w/o nickel, 73 w/o iron matrix was the most satisfactory from the standpoint of fabrication and over-all characteristics of the resulting sheet."
Date:
March 2, 1954
Creator:
Keeler, J. R.; Keller, D. L. & Cuddy, L. J.
System:
The UNT Digital Library
Temperature distributions in a reactor fuel plate
A report about the effects upon the fuel plate temperatures of introducing channel spacers into the proposed curved plate subassembly for the super critical water reactor.
Date:
1954
Creator:
Redmond, R. F.; Chastain, Joel W.; Long, J. K.; Jung, R. G. & Fawcett, Sherwood L.
System:
The UNT Digital Library
Temperature distributions in a reactor fuel plate
A report pertaining to heat-transfer characteristics , the supercritical water reactor, and flat fuel plates separated by cylindrical spacers perpendicular to the plates.
Date:
1954
Creator:
Long, J. K.; Chastain, Joel W.; Redmond, R. F.; Jung, R. G. & Fawcett, Sherwood L.
System:
The UNT Digital Library