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Atomic Energy Commission Reports
156
Hanford Works Reports
90
HW (Series)
63
University of California Radiation Laboratory Reports
52
BNL (Series)
44
Brookhaven National Laboratory Reports
44
Oak Ridge National Laboratory Reports
34
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19
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17
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Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores
In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.
Date:
March 2, 1953
Creator:
Abrams, Charles S.; Moulton, Harry D. & Viklund, Hans I.
Object Type:
Report
System:
The UNT Digital Library
Energy Spectrum of Deuterons Stripped From He3 and the Resultant Neutron Yield
The attenuation curve of the deuterons stripped from He3 has been measured with a Faraday cup. The corresponding curve at 190 Mev was fit by assuming that the deuterons were monoenergetic, with three processes taking place.
Date:
March 10, 1953
Creator:
Adelman, F. L.
Object Type:
Report
System:
The UNT Digital Library
Polymerization in Solid Solutions of Acrylamide in Propionamide
It has previously been shown that the polymer formed in solid state polymerization of acrylamide is amorphous in spite of the fact that the reaction takes place within a crystalline solid. The stage at which it becomes amorphous is not known at present. Work with dilute solid solutions of acrylamide in propionamide suggests that this occurs after the addition of, at most, a very few monomer units.
Date:
March 26, 1963
Creator:
Adler, G. & Reams, W.
Object Type:
Report
System:
The UNT Digital Library
Separation of Beryllium from Fission Products in a Nitrate Medium - Preliminary Experiments Using Solvent Extraction
Preliminary experiments using acetylacetone in the presence of ethylenediaminetetraacetic acid to separate major quantities of beryllium from fission products are reported. Using 2M beryllium solutions, decontamination factors of the order of 10/sup 3/ were obtained with trace quantities of the more important fission products. This is sufficiently encouraging for the work to be repeated at higher activity levels.
Date:
March 1963
Creator:
Aggett, J
Object Type:
Report
System:
The UNT Digital Library
State of Matter at High Pressure
Abstract. The region where exact thermodynamic description of the state of matter at high pressure and high temperature is possible is located. In the remaining region various approximate theories and empirical relations are discussed. These considerations are applied to hydrogen to locate the density and pressure at which the diatomic bond collapses. Also the approximate conditions are determined at which no bound electron states exist.
Date:
March 31, 1960
Creator:
Alder, Berni J.
Object Type:
Report
System:
The UNT Digital Library
Cost Estimation for Nuclear Reprocessing Plants : a Comparison of Methods
A comparison of methods of capital cost estimation used for nuclear fuel reprocessing plants shows that, because of the special nature and complexity of such plants, cost estimation methods for conventional chemical plants involving the use of cost factors are not applicable and will give low estimates. Cost factors which are available from other countries where reprocessing plants are installed should be used with caution since those factors apply only for the particular design philosophy used and pertain to industrial conditions which are different in this county. Capital cost estimation methods involving direct take-offs from detailed design drawings are necessary to obtain reliable estimates. The methods of estimating operating costs for nuclear reprocessing and conventional chemical plants are similar.
Date:
March 1962
Creator:
Alfredson, Peter George & Cairns, R. C.
Object Type:
Report
System:
The UNT Digital Library
Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate
From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."
Date:
March 1958
Creator:
Ames, Donald P. & Karraker, David G.
Object Type:
Report
System:
The UNT Digital Library
Density and Hydrogen Content of Uranium Oxide Cakes and Slurries
The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date:
March 22, 1960
Creator:
Amos, L. C.
Object Type:
Report
System:
The UNT Digital Library
Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program, Semiannual Report for Period July 1 - December 31, 1962
This technical report describes development work done on zonal centrifuge systems at the Oak Ridge National Laboratory and the Oak Ridge Gaseous Diffusion Plant during the period July 1 to December 31, 1962 under the Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program. A basic purpose of this project is to develop new methods for isolating virus particles associated with cancerous cells and tissues. Three classes of rotor systems capable of separating particles ranging in size from whole animal or plant cells to protein or nucleic acid molecules on the basis of either sedimentation rate or density alone have been developed. Experiments with phage particles indicate the feasibility of large-scale virus isolation by continuous-flow centrifugation, followed by isopycnic banding in cesium chloride and velocity sedimentation in sucrose - all steps being carried out sequentially in the same rotor. Zonal rotors using the reorienting gradient principle for molecular separations have been tested to 141,000 rpm (formula). Previous work on zonal centrifugation and future plans for this program are discussed.
Date:
March 4, 1963
Creator:
Anderson, N. G.
Object Type:
Report
System:
The UNT Digital Library
In-Pile Slurry Loop Program
The in-plie slurry loop work is now being considered as a joint program between the PAR project and ORNL. It is proposed that PAR design, fabricate and test the in-pile loops and that ORNL operate the loops in-pile, dismantle the loops after irradiation and made the appropriate measurements to determine the radiation effects. This report gives the objects of the slurry in-pile program and outlines the facilities and operations required to execute ORNL's part of this program.
Date:
March 8, 1957
Creator:
Arehart, T. A.; Compere, E. L. (Edgar L.); Ferguson, D. E.; Korsmeyer, R. B. & McBride, J. P.
Object Type:
Report
System:
The UNT Digital Library
Reactor Engineering Division Quarterly Report : December 1, 1952 Through February 28, 1953
Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, research, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date:
March 15, 1953
Creator:
Argonne National Laboratory. Reactor Engineering Division
Object Type:
Report
System:
The UNT Digital Library
Fission Product Activities in Irradiated Natural Uranium, Enriched Uranium, and Thorium
Calculated data and graphs describing the effects of batch thermal-neutron irradiations on the buildup of fission products in natural uranium, enriched uranium, and thorium are presented together with empirical equations and plots correlating total fission product activities and/or decontamination factors. Fluxes of 1012-1015 are considered.
Date:
March 28, 1956
Creator:
Arnold, E. D.
Object Type:
Report
System:
The UNT Digital Library
Disposition of Radiation Products and Energy Transfer in Radiobiological Processes
Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.
Date:
March 28, 1962
Creator:
Augenstine, L. G.
Object Type:
Report
System:
The UNT Digital Library
Numerical Solutions for Diffusion in a Sphere, Cylinder, and Plate
In calculating diffusion coefficients for gases diffusing from solids, the numerical solutions tabulated by Darken and Gurry, were found to lack the required precision, and the intervals between the arguments were too great to permit precise interpolations. Consequently the diffusion equation solutions of interest (diffusion from a sphere, cylinder, and plate, for the condition that the concentration of the diffusing species initially uniform) were re-evaluated. Computer programs for the three cases were written in FORTRAN for the IBM 7090. The solutions programmed are given in Crank. Values of the fractional completion were computed at approximately 0.01 increments, to the nearest 0.00001, and are tabulated in Table 1 to the nearest 0.0001. The table covers the fractional range from about 0.04 to 0.99. For smaller fractions satisfactory approximations are available. The table may be conveniently interpolated by plotting points about the region of interest and drawing a curve.
Date:
March 8, 1963
Creator:
Auskern, Allan
Object Type:
Report
System:
The UNT Digital Library
A Versatile Bubble-Chamber Track Measuring Stage
Technical report describing a bubble chamber film track measuring stage designed for maximum versatility that was build at Brookhaven National Laboratory. The report includes photographs and diagrams of the device.
Date:
March 1962
Creator:
Ayer, Frederick, II & Bolze, Ernest M.
Object Type:
Report
System:
The UNT Digital Library
A Bubble Chamber Track-Centering Device with Digitized Output
Technical report describing "A means for automatically determining the coordinates of a point at the center of a bubble chamber track." from the abstract.
Date:
March 1962
Creator:
Ayer, Frederick.; Pickup, Eric.; Rappe, Edwin F. & Wall, Gaylord.
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: March 1957
A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report work was reported on a completed study of the change in critical concentration and critical diameter with small changes in the physical and nuclear parameters of the reference design, reactor design #8 which incorporates an integral graphite core and core tank has been completed and distributed, and other work required for the design and construction of a LMFRE.
Date:
March 1957
Creator:
Babcock & Wilcox Company
Object Type:
Report
System:
The UNT Digital Library
The Surface Preparation of Uranium for X-Ray Diffraction Studies by the Spectrometer Technique
A report which describes a number of experiments conducted to compare the effects of different methods of surface preparation on x-ray diffraction patterns of uranium obtained by the spectrometer technique.
Date:
March 24, 1949
Creator:
Bach, J. H. & Burnham, J. B.
Object Type:
Report
System:
The UNT Digital Library
100-N Decontamination Facility Design Guide.
Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date:
March 8, 1960
Creator:
Bainard, W. D.
Object Type:
Report
System:
The UNT Digital Library
͟v͟ic-Dioximes as Analytical Reagents
This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.
Date:
March 19, 1962
Creator:
Banks, Charles V.
Object Type:
Report
System:
The UNT Digital Library
Stability Constants and Intrinsic Solubility of Several Nickel(II)-vic-Dioxime Complexes
This technical report discusses processes to study the stability constants and intrinsic solubility of several Nickel(II)-vic-Dioxime complexes.
Date:
March 19, 1962
Creator:
Banks, Charles V. & Anderson, Samuel
Object Type:
Report
System:
The UNT Digital Library
Tory II-A Instrumentation System : Brief Description
Abstract. The Tory II-A reactor is a small, air cooled, high power-density reactor which is to operate at quite high temperatures. Design of the reactor is essentially complete. First operation is scheduled for late 1960 at the Nevada Test Site of the Atomic Energy Commission. Since the reactor is unshielded, the control room which houses the recording and indicting equipment is located approximately two miles from the test bunker. Signals from reactor and facility transducers are amplified in the test bunker and transmitted by cable to the control point. The kinds of quantities measures include neutron flux level, temperatures, pressures, vibration amplitudes, strain and air mass flow rate. The recording and indicating system is centered around 258 channels of 1.5 cycle per second, pulse-width modulation tape recording equipment and 72 channels of 120 cps, analogue strip-chart records. In addition, there is a number of the usual meters, scalers and slow-response strip-chart recorders.
Date:
March 3, 1960
Creator:
Barnett, Charles S.; McDonald, Henry C. & Uthe, Paul M.
Object Type:
Report
System:
The UNT Digital Library
An Investigation of Scaling of Zirconium at Elevated Temperatures. Quarterly Status Report No. 11, December 2, 1955 to March 2, 1956
This technical report reports progress in the following areas: (1) Effect of scaling time; (2) Influence of specimen shape; (3) Effect of pretreatment; (4) Possible mechanism of growth; and (5) Future work.
Date:
March 13, 1956
Creator:
Barrett, C. A. & Evans, E. B.
Object Type:
Report
System:
The UNT Digital Library
Chemistry of the "Silver Reactor"
The use of a reactor charged with silver nitrate coated packing for removal of radio-iodine from the waste gases of Hanford chemical processing plants has been successful in removing approximately 99.5 percent of this activity. Studies by the Radiological Sciences Department indicated the desirability of further reducing the amount of radio-iodine released to the atmosphere. Therefore, this study was undertaken with the objectives of better understanding the inherent limitations to iodine removal by reaction with silver nitrate, and improving the efficiency of removal of iodine.
Date:
March 5, 1956
Creator:
Barton, G. B. & McClanahan, Jr., E. D.
Object Type:
Report
System:
The UNT Digital Library