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Investigations of Ion Exchange Methods for Recovery of Uranium From Liquors Produced by Acid Leaching of Gunnar Ore
An ion exchange testing program was completed on Gunnar acid leach liquors and pulps. A standard column system and a resin-in-pulp system, both using anion exchange resins, were investigated. The Gunnar leach liquors are readily amenable to the recovery of uranium by ion exchange.
Date:
June 15, 1954
Creator:
Schiff, Norman N. & Lower, George W.
Object Type:
Report
System:
The UNT Digital Library
Recovery of Uranium by Ion Exchange or by Uranous Phosphate Precipitation from Sulfuric Acid Leach Solutions Produced from Australian Davidite Ore Concentrates
Uranium ore from Radium Hill, South Australia was leached with hot sulfuric acid solutions and the uranium recovered from solution by uranous phosphate precipitation or by use of anion exchange resins.
Date:
June 9, 1952
Creator:
George, D'Arcy R.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Leaching Investigation of Ores From Radium Hill, South Australia
Leaching tests indicated high recoveries could be obtained by use of large quantities of sulfuric acid and boiling for relatively long periods. Filtration rates were satisfactory but large settling areas would be required to wash and thicken before filtering.
Date:
June 30, 1952
Creator:
Hollis, R. F.; Breymann, J. B. & Lynch, J. T.
Object Type:
Report
System:
The UNT Digital Library
An Integral Experiment to Measure the Tritium Production From Li7 By 14 Mev Neutrons in a Lithium Deuteride Sphere
A sphere of LiD 2 feet in diameter was irradiated by 2 x 10<sup>15 14 Mev neutrons. Samples of Li<sup>7 metal were positioned at various radii for the irradiation. An analysis of these samples for tritium led to a determination of the number of tritons produced by 14 Mev neutrons acting on Li<sup>7 in a LiD system.
Date:
June 1958
Creator:
Wyman, Marvin Eugene, 1921-
Object Type:
Report
System:
The UNT Digital Library
A Measurement of the [Lithium-7] Cross-Section for Several Neutron Energies From 4 to 15 Mev by Absolute Counting Techniques
A measurement of the [Lithium-7] reaction cross section by absolute counting of the tritium betas is described. The cross section was measured at several neutron energies between 4 Mev and 15 Mev. A comparison with results by emulsion techniques is given.
Date:
June 1958
Creator:
Wyman, Marvin Eugene, 1921- & Thorpe, Munson M.
Object Type:
Report
System:
The UNT Digital Library
Nonweapons Activities at Los Alamos Scientific Laboratory. Part III: Power Reactor Experiments
The work of the Laboratory has greatly expanded into applications of nuclear energy which are significant for national defense and security, but are not directly connected with weapons development. It was felt, therefore, that a description of the non weapons activities of the Laboratory would serve a useful purpose at this time. For classification reasons, it has been necessary to issue the report in three parts; the third part concerns power reactor experiments.
Date:
June 1956
Creator:
Glasstone, Samuel, 1897-1986
Object Type:
Report
System:
The UNT Digital Library
Some Experiments on the Precipitation of Plutonium Compounds From Triputyl Phosphate Solutions
The experiments described in this report were designed to explore the feasibility of precipitating plutonium from 35 percent TBP in Gulf BT using peroxide, fluoride, sulfide, sulfite, sulfate, cocalate, hydroxide, iodate and phosphate ions from anhydrous, dilute and concentrated aqueous sources.
Date:
June 11, 1956
Creator:
Maraman, W. J. & Mullins, L. J.
Object Type:
Report
System:
The UNT Digital Library
Nonweapons Activities at Los Alamos Scientific Laboratory. Part 1: Controlled Thermonuclear Reactions
The work of the Laboratory has expanded into applications of nuclear energy which are significant for natural defense and security, but are not directly connected with weapons development. It was felt, therefore, that a description of the nonweapons activities of the Laboratory would serve a useful purpose at this time.. For classification reasons, it has been necessary to issue the report in three parts; this is the first and is concerned with controlled thermonuclear reactions.
Date:
June 1956
Creator:
Glasstone, Samuel, 1897-1986
Object Type:
Report
System:
The UNT Digital Library
The Determination of Small Amounts of Thorium in the Presence of Uranium, Titanium, and Tungsten
Thorium is determined in uranium alloys by means of a fluoride separation followed by a complexometric titration. A nitric of hydrochloric acid solution of the alloy is neutralized to a pH of 2.0 to 3.0 and the thorium precipitated as thorium fluoride by the addition of hydrofluoric acid and ammonium fluoride using lanthanum as a carrier.
Date:
June 1955
Creator:
Willard, Hobart H. (Hobart Hurd), 1881-1974; Moses, Arthur W. & Gardner, Ross D.
Object Type:
Report
System:
The UNT Digital Library
Metallurgy Division Semiannual Progress Report for Period Ending October 10, 1955
Progress report of the Oak Ridge National Laboratory Metallurgy Division providing updates on various projects, experiments, and other work. This report includes a summary of nondestructive testing, physical chemistry of corrosion, fundamental physico-metallurgical research, HRP metallurgy, process metallurgy, metallurgical materials and processing, metallography, and ceramics research.
Date:
June 14, 1954
Creator:
Manly, W. D.
Object Type:
Report
System:
The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1956
This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and ether ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research.
Date:
June 13, 1956
Creator:
Jordan, W. H.; Cromer, S. J. & Miller, A. J.
Object Type:
Report
System:
The UNT Digital Library
Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field
In some recent experiments the ion density in a plasma was measured as a function of radial distance from a d-c arc source of ions for the magnetic field intensities from 2500 to 14000 oersted. The diffusion coefficient appeared to very inversely as the square of the magnetic field strength, D~1/H2. The absolute value of D was shown to be approximately that which would be predicted by the collision diffusion theory when account is taken of the shorting effect of the end walls. The purpose of this report is to continue the examination of ion diffusion in a plasma and field experimentally the relation between the diffusion coefficient and the neutral gas pressure for a constant magnetic field.
Date:
June 15, 1956
Creator:
Reidigh, Rodger V.
Object Type:
Report
System:
The UNT Digital Library
Laboratory Development of the Thorex Process
Changes made in the Thorex process flowsheet were a decrease in the extraction column acidity to decrease thorium losses and the addition of a second thorium solvent-extraction cycle to provide the increased decontamination required when thorium irradiated to 2000-4000 g of U233 per ton is processed. Bonded slugs could not be dissolved by the Thorex flowsheet procedure. Various laboratory scale studies on feed preparation, first-cycle variables, and radiation damage to the solvent are reported.
Date:
June 12, 1956
Creator:
Wischow, R. P. & Mansfield, R. G.
Object Type:
Report
System:
The UNT Digital Library
Chemistry Division Semiannual Progress Report for Period Ending June 20, 1955
Continued work on the adsorbability of metal complexes from concentrated LiCl solutions and LiCl-HCl mixtures on a strong-base anion-exchange resin further demonstrated the much higher adsorbability of these complexes from LiCl solutions than from HCl solutions. The effect is believed to be due to the formation of less strongly adsorbed undissociated chloro-complex acids in the case of the HCl solutions.
Date:
June 20, 1955
Creator:
Taylor, E. H. & Bredig, M. A.
Object Type:
Report
System:
The UNT Digital Library
Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955
The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-in. cyclotron, the absolute values of the electron capture and loss cross sections for 26-Mev nitrogen ions were obtained. The angular distribution of the cross sections for elastic scattering of nitrogen by nitrogen was measured at energies from 13 to 22 Mev. A double-focusing 90-deg magnet is being planned for use in identifying stable reaction products from nitrogen-induced reactions. The major components of the revised 44-in. test cyclotron were assembled and are being tested. Consideration is being given to the use of these components, along with a new 20,000-oersted magnet and a shielded cyclotron room, and if the tests are satisfactory the Laboratory will have available a machine which will accelerate N5+ ions to 81 Mev.
Date:
June 24, 1955
Creator:
Livingston, Robert S. & Howard, F. T.
Object Type:
Report
System:
The UNT Digital Library
The Role of Internal Conversion in the Study of Isomeric Transitions
A short review of the field of internal conversions. Isomeric transitions teach us many details of nuclear structure. In these studies electromagnetic theory is considered as a "tool". It is a quite quantitative tool in the case of "internal conversion" - a phenomenon which has been widely studied for many years. Internal conversion takes place in competition with γ-ray emission: a fraction of the nuclei in excited states decay by γ-ray emission, the remaining fraction by transferring the energy to K, or L, etc. electrons in the atomic shell. Thus the lifetime of an excited nuclear state depends on the internal conversion coefficient. As internal conversion must be expected to depend on the details of the electronic environment, the lifetime of an isomeric state depends on the state of chemical combination of the isomer - as was recently shown explicitly in one case, that of Te-99m(6hr.).
Date:
June 24, 1954
Creator:
Goldhaber, M.
Object Type:
Report
System:
The UNT Digital Library
Progress Report - Studies on the Propagation of Gamma Rays in Air
Initial rough measurements of the quality of the gamma radiation from Co-60 in air indicated agreement with the theoretical calculations of Spencer and Fano for an infinite water medium. Further experiments were performed, duplicating the conditions assumed in the calculations. Since the spectral region between 100 kev and 1 mev has already been examined by Hayward, it was decided to investigate in detail the region below 100 kev and above 1.0 mev. Total radiation dosage measurements were made in water using Victoreen ion chambers. The build-up factor was measured as a function of distance. Good agreement was obtained with the results of White. The spectrum below 150 kev was examined with a small NaI(Tl) scintillation counter and both the shape of the spectrum and the attenuation as a function of distance was in good agreement with the calculations. At distance less than 30 cm from the source the spectral shape changed, gradually broadening with the peak shifting to higher energies. The primary region above 1.0 mev was examined using a large NaI(Tl) crystal, and the gradual loss of resolution in the two primaries as a function of distance with an increase in lower energy events was shown. The measurements to …
Date:
June 30, 1953
Creator:
Bernstein, W. & Weiss, M. M.
Object Type:
Report
System:
The UNT Digital Library
Design Study for a 15-BeV Accelerator
This report is the culmination of a year of progress and planning in the high-energy particle field. During this year the Brookhaven Cosmotron has been successfully completed and brought into operation for research at 2.3 Bev. Preliminary experimental results with the copious output of π-mesons are in process of publication. Multiple production of mesons has been observed, a few V-particles detected, and the interactions of π-mesons in hydrogen have been studied. Yet it already appears that higher energies will be needed to produce and study the several new heavy particles detected in cosmic ray observations.
Date:
June 30, 1953
Creator:
Livingston, M., Stanley, Prof.; Ramsey, N. F., Prof.; Street, J. C., Prof.; Pound, R. V., Prof; Preston, W. M., Prof; Selove, W., Prof. et al.
Object Type:
Report
System:
The UNT Digital Library
Report of Invention The Preparation of Uranium Dioxide by Fused Salt Electrolysis
This is a report of what may be an invention in the preparation of uranium dioxide of a quality particularly useful for the fabrications of fuel elements for nutronic reactors.
Date:
June 25, 1959
Creator:
Lyon, W. L.
Object Type:
Report
System:
The UNT Digital Library
Gamma Heating in PRTR Gas Loop
It is being considered that the in-reactor portion of the test section of the PRTR Gas-Cooled Loop Facility consist, in part, of two concentric Inconel-X tubes. The outer tube is the main stress member, with 3.5 O.D. and a wall thickness of 0.065. The inner tube is 3.0 O.D. and has a wall thickness of 0.030. The inner tube provides an annular gas space to serve as thermal insulation.
Date:
June 23, 1959
Creator:
Reginbel, J.J.
Object Type:
Report
System:
The UNT Digital Library
Trough-Time Dissolver
Designing a dissolver safe for up to 5 per cent U.235 enriched NPF's and having a one a ton per day capacity is a fundamental problem of Hanford NPF Program. Two basic design concepts have so far evolved, both of which employ a recirculating system in which the fuel elements are placed in the critically safe geometry separated from the bulk of the solution in another vessel. In one concept the fuel elements are charged to a set of geometrically safe cylinders or tubes and solution is circulated through them/ In the other concept the fuel elements are placed on a flat tray while solution is sprayed over them. In the latter system, nuclear safety is obtained by avoiding submerged dissolution and the resulting neutron moderation by the solution.
Date:
June 26, 1959
Creator:
McKee, R.W.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Investigation of Alkaline Permanganate - Sodium Acid Sulfate for Decontamination of High Temperature Recirculating Systems.
Decontamination of stainless steel and carbon steel used in high temperature recirculation systems is currently being studied to obtain an effective and economical decontamination process for use in these systems. This report presents the preliminary investigation process which has demonstrated very effective decontamination and is low in cost.
Date:
June 10, 1959
Creator:
Oldham, W. A.
Object Type:
Report
System:
The UNT Digital Library
Program on the IBM 709 Digital Computer of the P3 Approximation to the Boltzmann Transports equation in Cylindrical Geometry
In formulating this general diffusion theory expression which represents the neutron balance in a nuclear chain reactor the following assumptions were made : (1) the medium through which the neutrons are diffusing has a low neutron capture cross section, (2) the region in which the flux distribute is being described is two or three mean free paths from strong sources and sinks or from a boundary. Certainly, is going to the lattice cell of a receptor, both of the above conditions are violated; fuel elements have a large absorption cross section and most lattice cells are only two or three mean free paths to is over-all sites
Date:
June 17, 1959
Creator:
Matsumoto, D. D. & Richey, C. R.
Object Type:
Report
System:
The UNT Digital Library
Decontamination Studies for HAPO High Temperature Reactor Recirculation Systems Process Report June 1958-June 1959
A means for decontaminating the primary system of recirculating type reactor is necessary to insure operation and maintenance. This recirculation system can be contaminated by fuel element rupture products and induced corrosion product activities.
Date:
June 10, 1959
Creator:
Perrigo, Lyle D., Jr.
Object Type:
Report
System:
The UNT Digital Library