Chemistry Division Quarterly Progress Report for Period Ending March 31, 1951 (open access)

Chemistry Division Quarterly Progress Report for Period Ending March 31, 1951

Quarterly technical report including reports on chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation. [From Abstract]
Date: May 10, 1951
Creator: Lind, S. C.; Boyd, G. E. & Bredig, M. A.
System: The UNT Digital Library
Homogeneous Reactor Experiment Quarterly Progress Report for Period Ending February 28, 1951 (open access)

Homogeneous Reactor Experiment Quarterly Progress Report for Period Ending February 28, 1951

Technical report covering the Homogeneous Reactor Experiment (HRE) reactor physics and engineering, out-of-pile corrosion, in-pile studies, recombination of hydrogen and oxygen, HRE chemical studies, experimental programs for the HRE, and long-range studies. [From Summary]
Date: May 18, 1951
Creator: Winters, C. E.; Secoy, C. H. & Thompson, W. E.
System: The UNT Digital Library
Aqueous Homogeneous Reactors for Producing Central-Station Power (open access)

Aqueous Homogeneous Reactors for Producing Central-Station Power

Report issued by the Oak Ridge National Laboratory discussing aqueous homogeneous reactors used in central-station power. As stated in the introduction, "it contains an evaluation of the potentiality of producing power only, as exhibited by aqueous homogeneous systems" (p. 6). This report includes tables, and illustrations.
Date: May 25, 1951
Creator: Briggs, R. B.; Haubenreich, P. N.; Sanders, J. P.; Aven, R. E.; Zapp, F. C.; Segaser, C. L. et al.
System: The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant (open access)

Decontamination of ORNL Purex Pilot Plant

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1952

This quarterly progress discusses the ongoing work at the Oak Ridge National Laboratory for the quarter ending in March 10, 1952. Topics discussed include reactor theory and design, shielding research, materials research, and includes appendixes with supplemental information.
Date: May 7, 1952
Creator: Briant, R. C.; Miller, A. J. & Cottrell, William B.
System: The UNT Digital Library
A Critical Review of the Literature on Pressure Drop in Noncircular Ducts and Annuli (open access)

A Critical Review of the Literature on Pressure Drop in Noncircular Ducts and Annuli

This report presents "Results of a critical literature review on pressure drop due to isothermal turbulent flow in noncircular geometries" (introduction).
Date: May 22, 1952
Creator: Claiborne, H. C.
System: The UNT Digital Library
Revised Z Tables of the Rach Coefficients (open access)

Revised Z Tables of the Rach Coefficients

From introduction: "54 tables are given of the Z coefficients."
Date: May 28, 1953
Creator: Biedenharn, L. C.
System: The UNT Digital Library
Analytical Chemistry Division Semiannual Progress Report For Period Ending April 20,1955 (open access)

Analytical Chemistry Division Semiannual Progress Report For Period Ending April 20,1955

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.
System: The UNT Digital Library
The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids (open access)

The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids

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.
System: The UNT Digital Library
Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954 (open access)

Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954

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 …
Date: May 20, 1955
Creator: Clewett, G. H & Drury, J. S.
System: The UNT Digital Library
Interim Evaluation of the Fluorox Process for UF4 and UF6 Manufacture (open access)

Interim Evaluation of the Fluorox Process for UF4 and UF6 Manufacture

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.
System: The UNT Digital Library
The ANCO System for Boron Isotope Enrichment Progress Report for Period Ending September 20, 1955 (open access)

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

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 …
Date: May 1, 1956
Creator: Healy, R. M.; Joseph, K. F. & Palko, A. A.
System: The UNT Digital Library
Bulk ThO2, a Reactor Material (open access)

Bulk ThO2, a Reactor Material

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.
System: The UNT Digital Library
Thorex Thorium Nitrate Product Specifications (open access)

Thorex Thorium Nitrate Product Specifications

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.
System: The UNT Digital Library
A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid (open access)

A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid

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.
System: The UNT Digital Library
Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93) (open access)

Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93)

To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system under study is the extraction of uranyl ion from water by a TBP solution. Considerable effort has been directed to eliminating leaks in the diffusion cell and testing the optical system/
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0) (open access)

Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0) (open access)

Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements (open access)

Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements

A study of the thermodynamic properties of dilute aqueous hydrochloric acid solutions at elevated temperatures by an electromotive force method was undertaken for several reasons. First, a great need for fundamental information at elevated temperatures was evident from the growing number of industries making use of aqueous solutions at elevated temperatures. Second, the use of the hydrogen electrode against the silver-silver chloride electrode in dilute hydrochloric acid solutions promised to give fundamental thermodynamic information on an important electrode system as well as on hydrochloric acid over a wide temperature range.
Date: May 1959
Creator: Greeley, Richard Stiles
System: The UNT Digital Library
Eurochemic Assistance Program: Status Report as of April 1, 1959 (open access)

Eurochemic Assistance Program: Status Report as of April 1, 1959

Considerable delay has occurred in getting ratification of the Eurochemic charter by 80% of the participating nations. The French, who were not expected to ratify the charter until an elected government was again established , actually ratified under de Gaulle late in 1958.
Date: May 5, 1959
Creator: Nicholson, E. L.
System: The UNT Digital Library
Flame Photometric Determination of Iron Parts I, II, III and IV (open access)

Flame Photometric Determination of Iron Parts I, II, III and IV

A study was made of a method for the flame photometric determination of iron. In Part I of this report, the flame emission spectrum of iron, measured by means of a Beckman Model DU spectrophotometer with a flame attachment, is compated to that measured with an ORNL high-sensitivity, recording, single-beam instrument, in order to determine which instrument is best suited for this application. Although it was found that the Beckman product has the higher resolving power over the wavelength region of 360 to 400mu, it does no posses the sensitivity or ease of operation of the ORNL instrument. On this basis, the ORNL flame spectrophotometer is used in subsequent tests. After selecting the best-suited instrument for the flame photometric determination of iron, it was necessary to establish the optimum operating conditions for this particular method. These conditions are described in Part II.
Date: May 6, 1959
Creator: Menis, Oscar
System: The UNT Digital Library
High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts I Through V. (open access)

High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts I Through V.

The technique of high-frequency titrimetry has been applied to the determination of thorium, uranium, sulfate, and free acid. In Part I of this report, the reproducibility of the method for the titration of standard solutions which contained 50mg of thorium in the absence of interferences is established. The coefficient of variation of the method, under these conditions, was found to be less than one per cent. In Part II, the effect of uranium on the high-frequency titration of thorium, as well as the application of the method to actual samples, is discussed. Uranium in a ratio of 5 to 1 to thorium can be tolerated. When the method is applied to the analysis of representative samples, the coefficient of variation is one per cent.
Date: May 11, 1959
Creator: Menis, Oscar
System: The UNT Digital Library
Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2 (open access)

Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2

After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF6) escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF6 product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The product met both chemical purity and activity specifications for product level UF6. Decontamination from fission products was essentially complete. A gross gamma D.F. was apparently limited by the low activity of the feed salt.
Date: May 11, 1959
Creator: Culler, F. L.
System: The UNT Digital Library
Uranyl Sulfate-Dovex 21K Anion Exchange: A Literature Survey, Review of Preliminary Data and Outline of a Proposal Experimental Program (open access)

Uranyl Sulfate-Dovex 21K Anion Exchange: A Literature Survey, Review of Preliminary Data and Outline of a Proposal Experimental Program

The system Dovex 21K and aqueous uranyl sulfate solutions were studied in the solution compositions range: 0-0.005 mol/liter uranyl sulfate, 0.15 mil/liter total sulfate, 0.02 mol/liter H2SO4 (pH 2).It is shown that UO3SO4 and/or UO2(SO4)2-/2 are sorbed on the resin to form R2UO2(SO4)2. It is surmized that these same species are also involved at high uranyl concentrations and pH 2 it is suggested that U2O5SO4, U2O5(SO4)2-/2, and R2U2O3SO4 species may be involved.
Date: May 14, 1959
Creator: Jury, S. H. & Adams, J. B.
System: The UNT Digital Library