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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 UOâ‚‚
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
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-UOâ‚‚ 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 UOâ‚‚-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
Terminal Report on the Radiolanthanum Laboratory
"The purpose of this present document is twofold: (1) To acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the Radio-lanthanum Process. (2) To define the terminal status of the design of this laboratory and its equipment."
Date:
July 21, 1950
Creator:
Figenshau, J. K.
Object Type:
Report
System:
The UNT Digital Library
Evaluation and Consolidation of Electrolytic Thorium
Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date:
June 15, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
Object Type:
Report
System:
The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions
Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 and 0.033 mm."
Date:
July 5, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Object Type:
Report
System:
The UNT Digital Library
Further Studies on Large-Batch Melting of Uranium
The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
Date:
July 11, 1955
Creator:
Rengstorff, George W. & Lownie, Harold W., Jr.
Object Type:
Report
System:
The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952
This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date:
August 5, 1952
Creator:
Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Object Type:
Report
System:
The UNT Digital Library
A Countercurrent Solid-Liquid Contactor for Continuous Ion Exchange
From abstract: "A continuous countercurrent solid-liquid contactor has been developed which retains the desirable features of the conventional fixed bed and gains the advantages of countercurrent flow. It can be adapted to many solid-liquid mass-transfer processes such as ion exchange, silica gel adsorption, and ore leaching."
Date:
September 19, 1952
Creator:
Higgins, I. R.
Object Type:
Report
System:
The UNT Digital Library