The Roll Cladding of Uranium With Aluminum (open access)

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 Refining of MgX and Other Uranium-Bearing Materials (open access)

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

From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
Date: August 31, 1950
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
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
Hydrogen Embrittlement of Zirconium (open access)

Hydrogen Embrittlement of Zirconium

Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium."
Date: August 22, 1952
Creator: Dayton, Russell Wendt; Schwope, A. D.; Muehlenkamp, G. T.; Saller, Henry A.; Dickerson, R. F.; Schwartz, C. M. et al.
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
Enamels and Enameling Techniques for Coating Uranium Slugs (open access)

Enamels and Enameling Techniques for Coating Uranium Slugs

From introduction: "This report describes research on the development of compositions and techniques for porcelain enameling uranium fuel slugs used in Hanford production reactors."
Date: August 2, 1955
Creator: Tripp, Harlan P.; Schultz, John; King, Burnham William, 1907- & Duckworth, Winston H.
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
MoSi₂-UO₂ Ceramics for High-Temperature Fuel Elements (open access)

MoSi₂-UO₂ Ceramics for High-Temperature Fuel Elements

This report follows a study that was aimed at the collection of experimental data needed to estimate the maximum safe temperatures and dispersed UO2 contents for MoSi2--UO2 fuel elements exposed to air.
Date: August 18, 1955
Creator: Gambino, John R.; Quirk, John F. & Duckworth, Winston Howard
System: The UNT Digital Library
Eddy-Current Inspection of a Possible PWR Fuel Element (open access)

Eddy-Current Inspection of a Possible PWR Fuel Element

The following report follows the inspections of a number of eddy-current instrument procedures. The objectives of these tests were to detect both weld defects and lack of integrity of the body of the fuel elements.
Date: August 22, 1955
Creator: Stutz, David E.; Gibbs, Richard L.; Dickerson, Ronald F. & Wenk, Samuel A.
System: The UNT Digital Library
Enamels for the Protection of Aluminum Cans for Uranium Slugs (open access)

Enamels for the Protection of Aluminum Cans for Uranium Slugs

The following report examines the most suitable enamels recommended for protection of aluminum slug cans.
Date: August 31, 1955
Creator: Schultz, John; Tripp, Harlan P.; King, Burnham William, 1907- & Duckworth, Winston H.
System: The UNT Digital Library
Extrusion Cladding of Uranium Fuel Plates (open access)

Extrusion Cladding of Uranium Fuel Plates

The following report describes two methods of extrusion cladding of uranium fuel plates that were investigated and evaluated.
Date: August 22, 1958
Creator: Fiorentino, Robert J.; Drennen, David C.; Slunder, Charles J. & Hall, A. M.
System: The UNT Digital Library
Segregation in Arc-Melted Uranium-Niobium Alloys (open access)

Segregation in Arc-Melted Uranium-Niobium Alloys

Report discussing a study aimed at pinpointing the cause of banding segregation in arc-melted uranium-niobium alloys and suggesting possible methods for eliminating banding.
Date: August 28, 1957
Creator: Dickerson, Ronald F.; Foster, Ellis L. & Chubb, Walston
System: The UNT Digital Library
Development of Cermet Fuel Elements (open access)

Development of Cermet Fuel Elements

Abstract: "Fabrication techniques for making metal-ceramic fuel elements containing 60 to 90 volume per cent of UN or UO2 in a Type 302B stainless steel matrix was investigated. A hot press-forging procedure was most successful for fabricating fuel cores with a density of 90 per cent of theoretical or better. This procedure consisted of sealing the cold-pressed core compacts in stainless steel picture-frame packs, heating to 1900 F, and pressing to a total reduction in thickness of 35 per cent. A pressure of approximately 50 tsi ores used. Specimens produced by this method were evaluated on the basis of their microstructure, modules if rupture, electrical conductivity, and resistance to thermal shock. Microscopic and macroscopic examination showed the presence of a continuous metal skeleton even in specimens containing 90 volume per cent fuel. The modulus of rupture at room temperature varied from 22,500 psi for a specimen cnotaining 63 volume per cent UO2. Both the electrical conductivity and resistance to thermal shock of UO2 were improved by the addition of a small volume of metal. Gas-pressure-bonding techniques appear promising for clodding these cores into composite elements."
Date: August 11, 1958
Creator: Paprocki, Stan J.; Keller, Donald L.; Cunningham, G. W. & Kizer, Donald E.
System: The UNT Digital Library