Fabrication of Dispersed Uranium Fuel Elements Using Powder-Metallurgy Techniques (open access)

Fabrication of Dispersed Uranium Fuel Elements Using Powder-Metallurgy Techniques

Abstract: "Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cost of UC, U2Tl, U3Si, or U6Ni dispersed in Zircology 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powder-metallurgy methods in such a manner that good core-to-cladding bonds and cores with uniform dispersions of discrete uranium-composed particles are obtained. From the standpoint of fabricability, elements containing UC is Zircology 2, UC in stainless steel, and UN in stainless steel are the most promising. The UN in stainless steel has the best corrosion resistance in 680 F degassed water; however, UC in stainless steel has the best resistance to corrosion in 700 F NaK."
Date: May 6, 1957
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
System: The UNT Digital Library
The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction (open access)

The Influence of Lubrication on the Compactability of Magnesium-Green Salt Blends for Bomb Reduction

The following report follows the procedures to compact blends of uranium tetrafluoride and magnesium, describing how lubrication of the compact effects the outcome of the blends.
Date: June 18, 1957
Creator: Paprocki, Stan J.; Carlson, Ronald J. & Smith, Edward G., Jr.
System: The UNT Digital Library
A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems (open access)

A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems

The following report follows an experimental study that was made on the mass transport of chromium in polythermal inconel-fluoride fuel systems, followed by the technique of adding radioactive chromium-51 to the system as either CrF3 in the salt or as elemental chromium in the solid phase.
Date: June 18, 1957
Creator: Price, Robert B.; Sunderman, Duane Neuman; Pobereskin, Meyer & Calkins, George D.
System: The UNT Digital Library
Examination of Factors Affecting the Quality of Vacuum Induction-Melted Uranium (open access)

Examination of Factors Affecting the Quality of Vacuum Induction-Melted Uranium

The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.
Date: July 3, 1958
Creator: Endebrock, Roy W.; Foster, Ellis L. & Dickerson, Ronald F.
System: The UNT Digital Library
Examination of Factors Affecting the Quality of Vacuum Induction-Melted Uranium (open access)

Examination of Factors Affecting the Quality of Vacuum Induction-Melted Uranium

The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.
Date: July 3, 1958
Creator: Endebrock, Roy W.; Foster, Ellis L. & Dickerson, Ronald F.
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
Topical report on spectrophotometric determination of small amounts of uranium in phosphate rock, shales and similar materials (open access)

Topical report on spectrophotometric determination of small amounts of uranium in phosphate rock, shales and similar materials

A report which provides procedures for sample decomposition and the determination of small amounts of uranium in the phosphate rocks and shales. Also, the cupferron and ether-extraction methods are discussed.
Date: 1947
Creator: Center, E. J.
System: The UNT Digital Library
Uranium recovery from a low-grade Katanga sulfide concentrate : topical report (open access)

Uranium recovery from a low-grade Katanga sulfide concentrate : topical report

A report which describes a variety of methods for processing a low-grade sulfide concentrate from the Congo. This concentrate consists primarily of sulfides of cobalt, nickel, and iron, plus about 10 percent uranium, present principally as uraninite.
Date: 1953
Creator: Bearse, A. E.; Ewing, R. A.; Sclar, C. B. & Pobereskin, M.
System: The UNT Digital Library