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The ANCO System for Boron Isotope Enrichment Progress Report for Period Ending September 20, 1955

Description: A new gas-liquid countercurrent system (the ANCO system from Anisole-Complex) for the enrichment of boron isotopes has been developed. It is believed that use of this systems will result in a considerably lower unit cost for enriched boron-10 than was previously possible. The system utilizes the exchange reaction between BF3 (gas) and BF3·anisole (liquid) to concentrate boron-10 in the liquid phase. The single stage isotopic separation factor for this system has been found to vary from 1.039 at 0°C to 1.029 at 30°C. The isotopic exchange reaction has been shown to be rapid. Vapor pressures of the complex as a function of temperature have been measured and the heat of formation of the complex determined. Laboratory experiments show that quantitative removal of the BF3 from the complex can be accomplished by heating. A complete miniature ANCO plant was constructed and operated in the laboratory to test the feasibility of the system. The system was found to operate efficiently with a minimum of attention, and to enrich the isotopes of boron as expected. Based upon the experience obtained with the laboratory ANCO unit, a pilot plant large enough to utilize a 6-inch diameter exchange column was designed. The design calculations of the major pieces of equipment are presented.
Date: May 1, 1956
Creator: Healy, R. M.; Joseph, K. F. & Palko, A. A.
Partner: UNT Libraries Government Documents Department
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Thorex Thorium Nitrate Product Specifications

Description: Activity and ionic impurity specifications are presented for Thorex thorium nitrate products. Two sets of specifications are given, one set for direct handling during refabrication of production reactor thorium metal slugs and the second for refabrication of future power reactor thorium metal elements by semi-remote technics. Consideration was given to the health hazard problems associated with each process step between the Thorex process and final refabricated source material in order to arrive at these specifications.
Date: May 24, 1956
Creator: Arnold, E. D. & Wischow, R. P.
Partner: UNT Libraries Government Documents Department
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Bulk ThO2, a Reactor Material

Description: Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processing of ThO2.
Date: May 24, 1956
Creator: Johnson, J. R. & Warde, J. M.
Partner: UNT Libraries Government Documents Department
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A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid

Description: Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be 6¢ per pound of HF.
Date: May 25, 1956
Creator: Marinsky, J. A. & Giuffrida, A. J.
Partner: UNT Libraries Government Documents Department
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Interim Evaluation of the Fluorox Process for UF4 and UF6 Manufacture

Description: The conversion of UNH to UF4 and UF6, utilizing moving-bed techniques, is being studied; sufficient progress has been made that an evaluation of the process is warranted. The procedures under study, the Fluorox Process, have three major advantages: (1) substitution of HF for high-cost fluorine, (2) considerable reduction in HF requirements, and (3) marked reduction in plant-size and mechanical complexity.
Date: May 26, 1955
Creator: Moore, J. E.
Partner: UNT Libraries Government Documents Department
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The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids

Description: Bench scale studies have been made of the recovery of uranium from acid leach liquors (and slurries) by solvent extracting with di (2-ethylhexyl) phosphoric acid in an organic diluent. Uranium may be stripped from the organic solvent by either alkaline or acidic reagents, the former having been studied in greater detail. On the basis of these tests, a recovery process may be considered which shows promise both from the standpoint of operation and chemical costs. Under proper conditions, vanadium can also be extracted by the di (2-ethylhexyl) phosphoric acid and stripping again may be accomplished with either acidic or alkaline reagents. Preliminary studies have been made of these possibilities. In addition to di (2-ethylhexyl) phosphoric acid, some other organophosphorus acids, have been cursorily examined in respect to their extraction and/or stripping performance.
Date: May 13, 1955
Creator: Blake, C. A.; Brown, K. B.; Coleman, C. F.; Horner, D. E. & Schmitt, J. M.
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Semiannual Progress Report For Period Ending April 20,1955

Description: The development of ionic methods for the determination of corrosion products in the highly radioactive Homogeneous Reactor (HR) fuels has been of major interest in the work of the Ionic Analyses Laboratory. Methods for the spectrophotometric determination of aluminum and for the polarographic determination of iron in HR fuels have been developed. The polarographic determination of molybdenum in uranyl sulfate solutions was studied. A polarographic method for the determination of zinc was developed. A fluorometric method for the determination of microgram amounts of fluoride was studied. Three organic reagents were investigated as precipitants for microgram quantities of zirconium in HR fuel. The automatic photometric titration technique was applied to the determination of thorium and of sulfate. A method was developed for the ionexchange separation and potentiometric titration of cobalt. The ultraviolet absorption spectra of technetium and rhenium were studied.
Date: May 6, 1955
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954

Description: New systems involving the exchange of boron between boron trifluoride and boron trifluoride addition compounds have been explored. These systems have large separation factors and potentially simple reflux mechanisms. A precise determination of this separation factor for the anisole-boron trifluoride system gave the value (see report). Boron exchange was found to occur between BF and BCl3. Several homogenous catalysts have been found which activate the hydrogen-water exchange, but none are adoptable to the production of deuterium because of the slow exchange rate. Platinum or platinum oxide may be usable as a heterogeneous catalyst with proper support or dispersion techniques. The high-pressure solubility of hydrogen in several amalgams was investigated in connection with a unique countercurrent exchange system. A proposed system involving isotopic exchange between lithium dipivaloylmethane in diethyl ether and lithium hydroxide in aqueous solution was shown to give little or no isotopic separation. Column studies of the carbonate system exchange reaction were concluded with a 40°C run. Slightly higher enrichment of N15 was obtained than at 30°C . The temperature dependence of all in this system was measured between 15 and 45°C. The factor increases with temperature, showing a tendency toward a maximum near 45°C. Isotopic exchange appears to be complete in less than 3 min. A qualitative examination was made of the carbonate system waste reflux reaction in laboratory equipment. No insurmountable difficulties are anticipated in connection with this reaction. The critical product-reflux reaction is being studied in pilot-scale equipment. Preliminary data are encouraging. Additional nitrogen exchange reactions have been studied to provide a broader basis for selecting a system for large-scale production of enriched nitrogen isotopes. A proposed system for enriching potassium isotopes was found to have a single stage separation factor of (see report). The single-stage fractionation factor between uranyl ion on Dowex 50 resin and …
Date: May 20, 1955
Creator: Clewett, G. H & Drury, J. S.
Partner: UNT Libraries Government Documents Department
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Weldability of Hayes Alloy #25

Description: Technical report describing the process to determine the fusion welding characteristics of Haynes Alloy #25 as applied to TLJ-100530, Corrosion Loops. Hayes Stellite Alloy #25 is a cobalt-base alloy for corrosion resistant high temperature applications. This material, when welded by the inert gas shielded tungsten arc method, produces sound ductile joints. Material thicknesses greater than 12 gauge require standard joint preparations, a V joint being preferred up to 1/4 inch and a U joint for greater thicknesses. Welding heat should be kept to a minimum followed by fast cooling. The molten metal is very fluid and may present difficulties when position welding.
Date: May 19, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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Braze Ring Mold for Sintering & Casting

Description: Technical report of an investigation to determine a suitable material for sintering and casting of braze rings. Braze rings afford an excellent means of preplacing braze alloy on tube to head joints of radiators, heat exchangers, and similar applications. A cast ring is especially desirable because of its increased strength. Previous efforts at casting had used welding grade carbon blocks with the desired ring cavities machined into their surface. Conclusion: Stackpole grade 331 electro-graphite provided the best results of the materials investigation. It is hard and more readily machinable with conventional tools than other grades. Carbon, in general, proved to be more satisfactory especially due its ease and speed of fabrication.
Date: May 14, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys

Description: Unclassified experimental data concerned with the oxidation characteristics of Nb and Nb-base alloys are presented. The bulk of the results is presented in tabular form and cataloged under laboratory name sub-headings. The theory of alloy development for oxidation resistance is discussed. Methods of evaluating oxidation behavior are outlined.
Date: May 20, 1959
Creator: Clough, W. R. (William Raymond); Hirakis, E. C. & Krutenat, R. C.
Partner: UNT Libraries Government Documents Department
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Braze Alloys v.s. Atmospheres : Final Report Project 1325

Description: Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer
Date: May 21, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

Description: "A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distributed source of thermal neutrons upon slowing down in the lattice."
Date: May 15, 1954
Creator: Laubenstein, R. A.
Partner: UNT Libraries Government Documents Department
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A Pebble-Bed Reactor for Stationary Power Plants

Description: A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the potential cost of electric power from this reactor is competitive with that from other reactor systems which have been proposed for the same application. The Po210 produced in the coolant presents a decontamination problem, but is also possibly a valuable by-producgt.
Date: May 15, 1954
Creator: Beeley, R. J.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Stratigraphy of the Park City and Phosphoria Formations and an Analysis of the Distribution of Phosphate in Utah

Description: "The Purpose of this paper is to present a preliminary discussion of the stratigraphy of the park city and phosphoric formations with special emphasis on the phosphatic parts and to discuss the distribution of phosphate in Utah. The Mississippian deposits are discussed only briefly because of the lack of new data concerning them"
Date: May 1957
Creator: Cheney, T. M.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Oregon

Description: Report documenting the suitability of Oregon for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: May 28, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Maryland

Description: Report documenting the suitability of Maryland for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: May 7, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Kansas

Description: Report documenting the suitability of Kansas for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: May 14, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Illinois, Volume 1 - Text

Description: Report documenting the suitability of Illinois for plant locations to produce synthetic liquid fuels, based on raw materials such as coal, natural gas, and oil shales.
Date: May 28, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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