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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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Some Properties of Stub Tuners Which Can Be Displayed On Smith Charts

Description: Use of the Smith chart in studying stub tuners is demonstrated. Several properties of the tuners are shown, and charts for various wave length spacings, tuning trajectories, and admittances are included.
Date: May 9, 1962
Creator: Walters, J. L.
Partner: UNT Libraries Government Documents Department
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Design of Reflectometers for Coaxial Lines Used at AGS LINAC

Description: This report describes the design procedure for a reflectometer or directional coupler to replace the probe part of the D07-1020 assembly used at the Brookhaven Alternating Gradient Synchrotron linac. Mathematical treatment and diagrams of various reflectometers are included.
Date: May 9, 1962
Creator: Walters, J. L.
Partner: UNT Libraries Government Documents Department
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The Ball Tuner Change Tables

Description: Technique used in deriving values of the linac ball tuner settings to produce various fields is discussed briefly, and tables showing ball tuner change numbers and values used in making up the ball tuner change numbers are given.
Date: May 3, 1962
Creator: Walters, J. L.
Partner: UNT Libraries Government Documents Department
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Synchrotron Oscillations

Description: Some numerical calculations have been done which permit the deduction of many properties of the synchrotron oscillation problem. For the presentation of the numerical results, it is useful to review the formulation framework to which the results are to be fitted. These are worked out for an arbitrary circular accelerator. The algebra woud have to be modified slightly to include straight sections but the numerical results are still useful.
Date: May 1, 1962
Creator: Hochman, E. H. & Barton, M. Q.
Partner: UNT Libraries Government Documents Department
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Uniformity Of Output From A Low-Amplitude Plane-Wave Nitroguanidine Explosive System

Description: In the Plowshare Program many calculations of the effects of underground explosions are made. Usually these are done on high-speed digital computers. The effects are calculated for ranges up to hundreds of meters from the explosion; at these ranges pressures become less than one kilobar. In order to make these calculations, information about the properties of the materials involved is required. Benedick [13] has developed a low-pressure, plane-wave lens using nitroguanidine. It was decided to use a similar lens in the Plowshare Program. A number of lenses were built using Benedick's technique. This report is of a study of simultaneity and pressure uniformity of these lenses, with some attempts at development of a reflection pressure vs particle velocity curve for them.
Date: May 12, 1964
Creator: Hearst, Joseph R. & Geesaman, L. B.
Partner: UNT Libraries Government Documents Department
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Silicon Nitride As A High-Temperature Radome Material

Description: LRL has the responsibility of demonstrating the feasibility of a reactor for use as a power plant for a low-altitude, high-Mach-number missile. This reactor is literally a very high power air heater which must work at temperatures in excess of 2000' F. The reactor is exposed to high loads so one of the primary problems is providing high temperature structure. Considerable effort has been devoted to developing ceramic structural elements. One of the materials considered for this purpose is silicon nitride. In ceramic structural elements operating over large temperature ranges, a major problem is coping with thermal stress. In this respect there is a similarity with the radome problem. The work on silicon nitride at LRL consisted of limited fabrication studies (principally for familiarization), measurement of properties of interest to the application, and funding of fabrication scale-up efforts.
Date: May 19, 1964
Creator: Wells, William M.
Partner: UNT Libraries Government Documents Department
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Cratering Experience With Chemical And Nuclear Explosives

Description: Over the past 13 years a considerable body of data on explosive cratering has been developed for application to nuclear excavation projects. These data were obtained from some ten cratering programs using chemical explosives (TNT or nitromethane) and seven nuclear cratering detonations. The types of media studied have ranged from marine muck to hard, dry basalt, although most effort has been devoted to craters in NTS desert alluvium and basalt. Considerable effort has also been devoted to the study with chemical explosives of the use of linear explosives and rows of point charges. This paper is intended to be a summary of these data and a statement of the understanding which has been developed from them.
Date: May 14, 1964
Creator: Nordyke, Milo D.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Prototype Fuel Elements for the Experimental Boiling Water Reactor and the Experimental Breeder Reactor

Description: The purpose of this program was to develop techniques and methods for producing fuel elements for the Experimental Boiling Water and Experimental Breeder Reactors. Methods for fabricating large tubes, flat plates, and small pins were investigated. The tube and plates contained U-5 w/o Zr-1.5 w/o Nb alloy and were designed for the EBWR. The pins contained U-2 w/o Zr alloy and were designed for the EBR. Cladding and end seal material of Zircaloy-2 was required for the water-cooled EBWR elements. Unalloyed zirconium was specified for cladding on the sodium-cooled EBR elements.
Date: May 1956
Creator: Sawyer, H. F.; Paynton, W. C.; Loewenstein, P. & Corzine, P.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report

Description: Measurement of radioactive carry-over was made on borax III operating at 300 psig and at power levels ranging from 4 to 14 mv. Decontamination factors of from 1.5 x 104 (at 14 mv) were obtained. These data are in essential agreement with those predicted by previous laboratory experimental work.
Date: May 2, 1956
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Mechanical and Physical Properties of Uranium: Chapter 8 of Nuclear Metallurgy Lectures

Description: A knowledge of the mechanical and physical properties of uranium is important in understanding and explaining its pile behavior. The effects of irradiation on the properties of uranium will be dealt with in another chapter. However, it is important to know and understand the pre-irradiation properties of uranium prior to investigating the effects of irradiation.
Date: May 10, 1955
Creator: Rueschen, R. E.
Partner: UNT Libraries Government Documents Department
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[Strategic planning grant proposal, May 19, 1993]

Description: A strategic planning grant proposal, submitted to the Getty Center for Education in the Arts, by D. Jack Davis and R. William McCarter. Attachments include a list of participants in different committees.
Date: May 19, 1993
Creator: Davis, D. Jack & McCarter, R. William
Partner: UNT Libraries Special Collections
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A Case of Rod Warping

Description: Warping of a rod by a variation in heat transfer coefficient around the periphery is considered. Estimates for some simple cases are given, and a more precise numerical calculation is carried out in ne instance.
Date: May 27, 1944
Creator: Murray, F. & Young, Gale Jay
Partner: UNT Libraries Government Documents Department
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The Diffusion Length of Thermal Neutrons in Uranium

Description: Measurements made in a uranium cylinder result in a mean value of 1.55 cm. for the diffusion length L for distances of 1 to 4 cm. from the base of the cylinder. Calculations give a value which agrees with the experimental result and show further that L increases from 1.40 to 1.63 cm. as the neutrons diffuse a distance of 5 cm. into the uranium.
Date: May 27, 1944
Creator: Hughes, Donald James, 1915-1960 & Bragdon, E. W.
Partner: UNT Libraries Government Documents Department
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