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Atomic Energy Commission Reports
159
Hanford Works Reports
70
University of California Radiation Laboratory Reports
60
HW (Series)
51
Oak Ridge National Laboratory Reports
38
BMI (Series)
25
Battelle Memorial Institute Reports
25
General Electric Company Atomic Power Reports
25
GEAP (Series)
24
UCRL (Series)
22
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Notes on the A-2-Compiler System
"An account is given of an extensive study of the A-2 Compiler System for the Remington Rand Univac digital computer. In particular, the following topics are discussed: application and performance of subroutines, segmenting, and introduction of subroutines to the library."
Date:
July 15, 1957
Creator:
Lanza, G. &
Object Type:
Report
System:
The UNT Digital Library
Betatron Oscillation Frequency Shift Due To "N-Errors"
"Expressions are found to relate DELTA gamma to the n-errors.'' It is demonstrated that the integral n-value concept'' is of no use in the present case. A modification of integrated n-value'' is suggested."
Date:
July 1, 1957
Creator:
Lanza, G. & Steffen, Klaus G.
Object Type:
Report
System:
The UNT Digital Library
A Regulated Power Supply for a High Current Magnet
Current regulation of a Bitter type electromagnet powered by a 10 kw. motor-generator set has been achieved by control of the generator exciting field. An error signal, obtained by comparing the voltage drop across a series resistor in the magnet circuit with a reference voltage, is fed back with appropriate amplification to the grids of series tubes in the generator field supply. Magnetic fields from 400 gauss to 10 kilogauss in a fixed gap (1.5 in. width and 3.5 in. diameter) are obtainable with regulation to 3 parts in 104 over the major part of this range.
Date:
July 1959
Creator:
Block, Richard B.
Object Type:
Report
System:
The UNT Digital Library
Technical Progress Report, University of Illinois, Graduate College, Digital Computer Laboratory, July 1959
This technical report covers five areas: (1) High-speed computer program; (2) Mathematical methods; (3) ILLIAC use and operations; (4) IBM 650 use and operation; (5) General laboratory information.
Date:
July 1959
Creator:
Taub, A. H., 1911-1999
Object Type:
Report
System:
The UNT Digital Library
Path of Triple Point for spherical Shocks Above a Rigid Plane
Paths of trip points of Mach reflections produced by 0.5-oz pentolite detonations have been observed for various burst heights. The slopes, Y, at points on the curved path are found to vary from values of Y predicted from plane shock wave data. This discrepancy is attributed to the shock strength conditions at the early inception of the Mach reflection, which later influence the triple point equilibrium, and in lesser degree to radius of curvature effects.
Date:
July 13, 1954
Creator:
Todd, Jay. Jr. & Schellenbaum, Ralph L.
Object Type:
Report
System:
The UNT Digital Library
Thickness Vibrations in Long Rods of Barium Titanate
A theoretical analysis of the thickness vibrations in long thin rods of barium titanate is presented. The theoretical results are checked experimentally and their meaning discussed.
Date:
July 29, 1955
Creator:
Stephenson, C. V.
Object Type:
Report
System:
The UNT Digital Library
The Shape of a Shock Wave Derived from a Spherical Shock Wave Incident on a Concave Wedge
When a one-half ounce spherical charge of high explosive is detonated over a flat plane bounded by a 5 degree incline, the type of phenomenon encountered depends on the distance from ground zero to a beginning of the incline. If this distance is 48" the wave assumes a smooth contour on the plane. Detailed investigation of the shock velocity above the plane reveals that there is a pressure gradient along the shock front for a considerable region which replaces the usual triple point.
Date:
July 7, 1954
Creator:
Todd, Jay, Jr. & Schellenbaum, Ralph L.
Object Type:
Report
System:
The UNT Digital Library
Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element
It is assumed that when a hole appears in the cladding of a reactor fuel tube the fission products in the space between the fuel and the cladding will diffuse towards the hole. There they are swept away by the flow of steam past the hole. The process of diffusion is assumed to be governed by the ordinary diffusion equation with the boundary condition that the density of the fission products is zero at the surface of the hole. The diffusion equation is solved for the case of steady-state emission for a number of geometrical arrangements: long slit in plane surface; long slit in cylindrical surfaces circular hole in plane surface; circular hole in cylindrical surface; hole at end of cylindrical fuel rods and diffusion space of variable thickness. The time dependent solution of the diffusion equation is also found for a planar diffusion space. The effect of a temperature gradient is discussed.
Date:
July 26, 1956
Creator:
Helstrom, Carl W.
Object Type:
Report
System:
The UNT Digital Library
A Numerical Integration Scheme for Problems Involving Contour Representations
The definition of the Lebesgue integral is used to develop a numerical integration method in which the integral is evaluated directly from a contour plot of the function. It is useful in working from weather maps, potential surfaces, etc., but was particularly designed to assist in reducing blast diffraction space-time diagrams to simple, meaningful quantities.
Date:
July 6, 1955
Creator:
Hudson, C. C.
Object Type:
Report
System:
The UNT Digital Library
Principles and Techniques of Ultrasonic Inspection
Ultrasonic inspection for subsurface flaws is widely used in American industry. This report reviews the general principles and specific techniques of ultrasonic testing. The information is based on a review of the technical literature plus the experience of the Quality Assurance Department at Sandia Corporation in applying this nondestructive testing technique to quality evaluation programs.
Date:
July 2, 1953
Creator:
Psillas, H. C. & Ballard, D. W.
Object Type:
Report
System:
The UNT Digital Library
Datatron digital Computer Program for least-Squares Analysis of Variance
A digital computer program for calculating least-squares solutions and making analyses of variance of sets of overdetermined linear equations is described. The entire code is reproduced with sufficient description of the program to enable anyone familiar with the Electrodata Datatron Computer to use it for similar problems.
Date:
July 1955
Creator:
Rollett, J. S. (John Sidney)
Object Type:
Report
System:
The UNT Digital Library
The Mass Spectrum of Methane and the Energy Levels of the Fragment Ions and Radicals
A MO calculation of the electronic states of CH4, CH3, CH2, CH, and their respective ions provided the basis for the application of correlation rules to an analysis of the existing appearance potential data for methane. An interpretation of the methane mass spectrum has been proposed which is based on the high value of the heat of sublimation of carbon. It is shown that the excited electronic states of the molecule- and radical-ions are prominent in the decomposition reactions.
Date:
July 1955
Creator:
Krauss, Morris; Wahrhaftig, Austin L. & Eyring, Henry, 1901-1981
Object Type:
Report
System:
The UNT Digital Library
Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel
The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energies of 11-19 ft-lb. Testing of as-received material used in the lower closure head indicated that the NDT temperature was 50°F which was equivalent to an average Charpy-V-notch impact energy of 12 ft-lb. After normalizing and stress-relieving this material, in order to more closely approximate the final condition of the reactor vessel, NDT was reduced to less than 10°F.
Date:
July 23, 1959
Creator:
Thurber, W. C. & Lamartine, J. T.
Object Type:
Report
System:
The UNT Digital Library
The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin
The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date:
July 8, 1959
Creator:
Bresee, J. C.
Object Type:
Report
System:
The UNT Digital Library
Determination of Oxygen in Oxide Films by Neutron Activation Analysis
Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities masked F18 in the aluminum. It is concluded that a 1 A (0.01 Όgm/cm^2) oxide film thickness may be measured by a neutron irradiation at a flux of 10^14 n/cm^2/sec but chemical separation of induced radioactivity from the bulk metal is essential.
Date:
July 15, 1959
Creator:
Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
Determination of Li6 in Aqueous Solution by Neutron Activation Analysis
A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date:
July 10, 1959
Creator:
Winchester, J. W. & Bate, L. C.
Object Type:
Report
System:
The UNT Digital Library
Time Dependence of the Beam in the 86-Inch Cyclotron
In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date:
July 29, 1959
Creator:
Goodman, C. D.
Object Type:
Report
System:
The UNT Digital Library
Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers
Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employed in the tests which could clear the remaining tubes.
Date:
July 21, 1959
Creator:
Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Object Type:
Report
System:
The UNT Digital Library
A Parametric Study of a Gas Cooled Reactor
The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date:
July 24, 1959
Creator:
Epel, L. G.
Object Type:
Report
System:
The UNT Digital Library
PRFR Pilot Leaching Plant - Preliminary Process Design
The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date:
July 23, 1959
Creator:
McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
Multiplication Measurements with Highly Enriched Uranium Metal Slabs
A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date:
July 27, 1959
Creator:
Mihalczo, J. T. & Lynn, J. J.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of the PRFR Pilot Leaching Plant - Preliminary Process Design
The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior.
Date:
July 23, 1959
Creator:
McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
Multigroup Diffusion Theory Calculations for Recent Critical Experiments
In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentrations detailed neutron balances and a comparison with elementary theory are included. The agreement between the calculated and experimental multiplication constants is excellent for the multigroup calculation but only fair for the elementary calculation. The latter method overestimates the fast leakage so that the computed multiplication constant is less than that found experimentally.
Date:
July 21, 1959
Creator:
Nestor, C. W., Jr
Object Type:
Report
System:
The UNT Digital Library
Run 300A-B Slurry Run of 300A Pump and Loop
The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ÂșC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300 gpm.
Date:
July 2, 1959
Creator:
Moyers, J. C.
Object Type:
Report
System:
The UNT Digital Library