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Stepwise Calculation for the Determination of the Number of Transfer Units in Countercurrent Extraction Columns
Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."
Date:
September 12, 1949
Creator:
Burns, W. A. & Eschbach, E. A.
Object Type:
Report
System:
The UNT Digital Library
Special Irradiation of Temperature-Indicating Liquid: Final Report--Production Test 105-266-P
A report discussing an experiment conducted to determine the effect of radiation on the melting point of Tempilaq, a commercially available, temperature-indicating liquid.
Date:
August 18, 1949
Creator:
Carbon, M. W.
Object Type:
Report
System:
The UNT Digital Library
The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts
Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.
Date:
January 27, 1950
Creator:
Thorburn, R. C.
Object Type:
Report
System:
The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date:
September 29, 1952
Creator:
Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Object Type:
Report
System:
The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date:
September 29, 1952
Creator:
Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Object Type:
Report
System:
The UNT Digital Library
The Ductility of Brazed Stainless Steel Joints
Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date:
July 8, 1953
Creator:
Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Object Type:
Report
System:
The UNT Digital Library
Extrusion Cladding of Fuel Element
From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."
Date:
March 22, 1955
Creator:
Slunder, C. J.; Fiorentino, R. J. & Hall, A. M.
Object Type:
Report
System:
The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding
Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date:
May 4, 1955
Creator:
Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type:
Report
System:
The UNT Digital Library
Ceramic Investigations of UO₂
This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date:
June 16, 1955
Creator:
Allison, Adrian G. & Duckworth, Winston H.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Feasibility of Using Scintillating Fibers for Low Energy Beta Counting: Quarterly Report Number 1, June - September 1961
From introduction: "A detector system with the advantages of a liquid counter, but without the severe requirements on sample preparations, has been devised and is the basis of the present experimental investigation."
Date:
January 5, 1962
Creator:
Preston, C.
Object Type:
Report
System:
The UNT Digital Library
Scintillation Spectrometer Measurements of Capture Gamma Rays From Natural Elements: First Quarterly Report
From abstract: "The objective of this program is to make a compilation of neutron capture gamma ray spectra of the naturally occurring elements, covering both the low and high energy region, using Na I(TI) scintillation detectors...During this phase of the program a detection system, together with its associated shielding was constructed and tested."
Date:
October 4, 1961
Creator:
Greenwood, Reginald C. & Stone, C. A.
Object Type:
Report
System:
The UNT Digital Library
Studies of reactor containment : bi-monthly progress report, May to June 1962
Report discussing the progress made on various research programs at the Armour Research Foundation during the period from May to June 1962.
Date:
1962~
Creator:
Lieberman, P.; Anfinsen, L.; Botten, L.; Eichler, J. B.; Reba, I.; Schuyler, F. L. et al.
Object Type:
Report
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-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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
The Properties and Heat Treatment of Zirconium-Uranium Alloys
From Abstract: "The heat treatment and mechanical properties of four zirconium alloys...were investigated. Tensile, hardness, Jominy end-quench, and metallographic data constitute the basis for much of the report. Other data reported include the results of high-temperature creep, tensile, hardness, cold rolling, thermal-cycling, and dynamic-modulus tests." A connection is made between the behavior of these four alloys and more alloys in the zirconium-uranium system.
Date:
January 10, 1955
Creator:
Chubb, Walston; Muehlenkamp, G. T. & Manning, G. K.
Object Type:
Report
System:
The UNT Digital Library
A Study of Aluminum-Uranium Alloys
Report discussing the redetermination of liquids for aluminum alloys containing 13 to 25 w/o uranium by metallographic examination, thermal analyses, and electrical resistance measurements. In addition, phase diagrams and a method for producing sound, homogeneous aluminum 16 w/o uranium alloy sleeve castings are presented.
Date:
January 19, 1956
Creator:
Saller, Henry A.; Dickerson, Ronald F.; Rough, Frank A.; Foster, Ellis L.; Bauer, Arthur A. & Lulay, John R.
Object Type:
Report
System:
The UNT Digital Library
Solid-Phase-Reaction Studies of Control-Rod Materials
Report discussing experiments on the interaction of neutron-absorber materials and metal matrix materials used in the fabrication of control rods, such as "boron, cadmium, and some of the rare-earth elements such as gadolinium and europium...In order to evaluate the reactions that might occur during fabrication and use, experiments were carried out in which combinations of the various control materials were heated in intimate contact with the several matrices at elevated temperatures."
Date:
March 9, 1956
Creator:
Gerds, Arnold F. & Mallett, Manley William, 1909-
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During August, 1956
Report discussing the progress of research projects at Battelle Memorial Institute relating to civilian applications during August 1956.
Date:
September 4, 1956
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Thermal Distortion of SAR Hafnium Control Rod
Abstract: The thermal distortion of a Y-shaped hafnium control rod heated by arrays of individually controlled radiation heaters was studied. The large axial and radial temperature gradients specified for this control rod were easily obtained with the radiation-heating method. The distortion, as measured with dial indicators, amounted to a 2-mil movement of the free end of the rod in the direction of the coolest blade.
Date:
June 27, 1956
Creator:
Goldthwaite, William H.; Allen, C. Malcolm & Fawcett, Sherwood L.
Object Type:
Report
System:
The UNT Digital Library
Survey of Refractory Uranium Compounds
Abstract: Chemical and physical data on twenty binary uranium compounds that may prove suitable for refractory nuclear fuels were assembled. The compounds were those with aluminum, boron, carbon, iron, nickel, nitrogen, silicon, or sulfur. Too little is known at this time about the compounds to evaluate any of them for fuel. The program is being extended in an effort to provide the needed data.
Date:
August 7, 1956
Creator:
Loch, Luther D.; Engle, Glen B.; Snyder, M. Jack & Duckworth, Winston Howard
Object Type:
Report
System:
The UNT Digital Library
Survey of Materials for Supercritical-Water Reactor
Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.
Date:
November 27, 1953
Creator:
Udy, Murray C. & Boulger, Francis W.
Object Type:
Report
System:
The UNT Digital Library
Uranium Migration in UO₂-Bearing Ceramics
This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date:
September 4, 1953
Creator:
Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
Object Type:
Report
System:
The UNT Digital Library
Redox : Analytical Research Group Report [for] March and April 1949
Report discussing the results of research conducted by the Hanford Works Analytical Research Group during the period from March 1949 to April 1949.
Date:
June 21, 1949
Creator:
Schmidt, H. R.
Object Type:
Report
System:
The UNT Digital Library