6 Matching Results

Results open in a new window/tab.

Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys (open access)

Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys

Abstract: "The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum-35 w/o uranium were investigated. Initial investigations were concerned with the effects of 3 w/o ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 w/o level, additions of germanium, silicon, tin or zirconium inhibited the formation of UAl4 and thereby increased the content of the aluminum matrix in the alloy. It was also noted that these additions decreased the pressures required for extruding, and the tin addition also improved the homogeneity of cast shapes. Lead and palladium also improved the homogeneity of the cast material; however, neither of these was an effective inhibitor of UAl4 and free lead was detected in the alloy to which lead had been added at the ternary. From these studies it appears that tin and zirconium are as effective as silicon in enhancing the fabricating characteristics of aluminum-35 w/o uranium alloys, and may prove superior when evaluated on the bases of casting qualities and recycling characteristics."
Date: October 27, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
System: The UNT Digital Library
Canning graphite for gas-cooled reactors (open access)

Canning graphite for gas-cooled reactors

From abstract: "A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen-oxygen atmosphere"
Date: 1959
Creator: Paprocki, Stan J.; Carlson, Ronald J. & Bonnell, Paul H.
System: The UNT Digital Library
Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element (open access)

Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element

The following report presents neutron-flux measurements made with a concentric-cylinder element (Mark II) and includes axial, radial, and peripheral flux distributions.
Date: January 29, 1959
Creator: Anno, James N.; Fairand, Barry P. & Chastain, Joel W., Jr.
System: The UNT Digital Library
The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates (open access)

The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates

From introduction: "This report deals with a part of the research and development studies which preceded the manufacture of fuel elements for the Gas Cooled Reactor Experiment (GCRE)." The studies evaluate the effects of varying the type and size of UO2 particles, stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures and atmospheres, roll-cladding temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures has been made for UO2 stainless steel dispersion fuel elements."
Date: February 18, 1959
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
System: The UNT Digital Library
Centrifugal Casting of Aluminum-Uranium Alloys (open access)

Centrifugal Casting of Aluminum-Uranium Alloys

"Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75 per cent of the original charge. The major losses occurred in the pouring spout-and-cup assembly. This loss is relatively unaffected by the casting length; and, therefore, coatings of greater length than 26 in. should results in even greater recoveries.
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
System: The UNT Digital Library
Shielding Studies on Salt Slabs, Gadolinium, and Water (open access)

Shielding Studies on Salt Slabs, Gadolinium, and Water

Review of a study regarding a lid-tank shielding facility's properties, including fast-neutron and gamma dose rates and thermal-neutron fluxes, which were mapped in a symmetry plane. The removal cross section of gadolinium was determined through comparison with various other materials.
Date: October 7, 1959
Creator: Klingensmith, Raymond W.; Epstein, Harold M. & Chastain, Joel W.
System: The UNT Digital Library