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
Theoretical Studies of the Solidification of Uranium Castings (open access)

Theoretical Studies of the Solidification of Uranium Castings

Report discussing a method of evaluating factors relevant to the creation of sound uranium castings. From abstract: "A mathematical model has been developed to calculate the time-temperature relationships in a cylindrical uranium casting during its solidification. Finite-difference equations are used, and the solution is obtained by use of a digital computer."
Date: July 11, 1958
Creator: Fletcher, Billie L.; Foster, Ellis L., Jr.; Franklin, Charles K.; Lechler, Andrew; Schwartz, Benjamin L. & Dickerson, Ronald F.
System: The UNT Digital Library
The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium (open access)

The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium

This report discusses a study regarding the properties of uranium with added chromium, silicon, or titanium. This study was conducted in order to evaluate the effects of alloying on the mechanical properties of base metal.
Date: January 30, 1956
Creator: Saller, Henry A.; Rough, Frank A. & Chubb, Walston
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
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
The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service (open access)

The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service

From summary: "This report covers an experimental investigation into the fabrication of various potential fuel-element materials and the testing of these materials for compatibility with structural metals at 1090 C (2000 F)."
Date: October 8, 1951
Creator: Saller, Henry A. & Stacy, J. T.
System: The UNT Digital Library
Neutron-Flux Measurements in a Flat Plat Fuel Element (open access)

Neutron-Flux Measurements in a Flat Plat Fuel Element

The following report presents neutron-flux measurements with the Mark I element, which include neutron-flux distribution and flux depression within the element.
Date: October 31, 1957
Creator: Morgan, Walter R.; Anno, James N., Jr. & Chastain, Joel W., Jr.
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
A study of the dip coating of uranium sheet with aluminum-silicon alloy (open access)

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
Hazards Summary Report for the Reflector-Control Critical-Assembly Experiments (open access)

Hazards Summary Report for the Reflector-Control Critical-Assembly Experiments

This report analyzes the stability and feasibility of a reflector-control system for a boiling heterogeneous reactor.
Date: February 12, 1957
Creator: Jankowski, Francis J.; Hogan, William S.; Redmond, Robert F.; Chastain, Joel W. & Fawcett, Sherwood L.
System: The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2 (open access)

Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2

From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
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
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
Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment (open access)

Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

From introduction: "On February 1, 1956, Batelle was awarded a contract by the Army Reactor Branch (ARB) to select, develop, and test core materials which could be used successfully in conducting a Gas Cooled Reactor Experiment (GCRE). The prime objective of the GCRE would be to evaluate small portable reactor systems for military application...The present report is concerned with the GCRE activities at Batelle during approximately the 7 months' period following the first report of this series, BMI-1133. It is primarily concerned with a detailed evaluation of the reference materials as well as of the impact of one material upon the other."
Date: July 11, 1957
Creator: Keller, Donald L.
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