Serial/Series Title
Atomic Energy Commission Reports
1,476
AEC research and development report
571
TID
415
Brookhaven National Laboratory Reports
372
BNL (Series)
369
Oak Ridge National Laboratory Reports
278
Report (U.S. Atomic Energy Commission)
251
United States Geological Survey Reports
216
University of California Radiation Laboratory Reports
215
UC (Series)
211
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3,580 Matching Results
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Strontium Sorption Studies on Crandallite
Abstract: "Crandallite ores may be useful in the treatment of nuclear waste solutions because of their reactivity with strontium in weakly acid solutions and in alkaline solutions containing aluminum. The exchange capacity of the crandallite samples studies is not very high, being 6-10 miliequivalents of strontium and 2 milliequivalents of cesium per 100 grams of active phosphatic material. However, strontium removal is many times more effective from alkaline solutions, precipitation being the dominant mechanism. The removal of strontium is even more complete in alkaline solutions containing aluminate ions."
Date:
June 1960
Creator:
May, Irving; Schnepfe, Marian M. & Naeser, Charles R.
Object Type:
Report
System:
The UNT Digital Library
A Study for the Feasibility for the Large Sale Recovery of Ionium (Thorium-230) from the Uranium Ore Milling Industry in the United States
Over the past ten years, there has been considerable interest and expenditure on the recovery of ionium (thorium-230) from certain residues accumulated from the World War II uranium process at St. Louis, Missouri. Most of these efforts were reported in the classified literature. However, an unclassified report was issued recently by the Mallinckrodt Chemical Works on the plant design for ionium recovery. A review of the earlier efforts shows that consideration of ionium recovery was limited to the St. Louis residues. At that time the development of a substantial U. S. uranium ore milling industry had not yet been achieved.
Date:
June 1, 1960
Creator:
Rohrmann, C. A.
Object Type:
Report
System:
The UNT Digital Library
Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959
From abstract: This paper discusses the use of high flux reactors to remove a number of deficiencies in the knowledge of the interaction of neutrons with matter.
Date:
June 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Theory Of Emulsion Track Structure
The statistical behavior of measured track quantities, gap density, gap length coefficient, and lacunarity is studied. The transformations which give the expectation values of track quantities on inclined tracks are then found.
Date:
June 1960
Creator:
Barkas, Walter H. (Walter Henry), 1912-1969
Object Type:
Report
System:
The UNT Digital Library
Phase Diagrams of Zirconium-Beryllium and Related Systems
Introduction. The phase diagram data reported in this paper were obtained during an investigation of the beryllium-metal compounds of the titanium group transition elements. Several compounds in these systems had been previously reported but their compositions and structures were not all known. In the course of this study many details of the phase diagrams of the system were observed. Tentative diagrams consistent with this data will be presented.
Date:
May 31, 1960
Creator:
Bedford, Ray Gilbert, 1928-
Object Type:
Report
System:
The UNT Digital Library
Effect of Superheat and Moisture Separation on the SM-2 Design
From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."
Date:
May 27, 1960
Creator:
Phelps, E. F.
Object Type:
Report
System:
The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.
Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date:
May 27, 1960
Creator:
Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Object Type:
Report
System:
The UNT Digital Library
Observations on a Zircaloy-Uranium-Aluminum System at High Temperatures
A brief series of experiments was performed to study the high temperature reaction of the Zircaloy-uranium-aluminum system at the request of Reactor Engineering Operation, Irradiation Processing Department. Knowledge of the high temperature behavior of this combination of materials is important to the evaluation of reactor behavior during possible accidental over-heating of a fuel channel.
Date:
May 27, 1960
Creator:
Scott, A. J.
Object Type:
Report
System:
The UNT Digital Library
Experiments With Pulsed Magnetic Cusps
Experiments with a simple pulsed magnetic field in cusped geometry are described. The plasma is generated inside the containment region rather than injected from an external source. It was found that creation of the plasma by a linear pinch discharge is most successful. Only qualitative studies have been carried out so far, using time-resolved visual observation of the plasma. Well-defined plasma bodies located in the central region between the cells were photographed. In order to make them clearly visible, a few percent of argon was added to the hydrogen.
Date:
May 26, 1960
Creator:
Watteau, Jean-Paul H.
Object Type:
Report
System:
The UNT Digital Library
Some Properties of Vanadium Group Beryllides
Vanadium group beryllides were prepared and studied by x - ray powder diffraction and crystallographic methods. Properties included phase studies, sintering studies, vapor pressure measurements, and thermal diffusivity measurements,
Date:
May 25, 1960
Creator:
Krikorian, Oscar Harold
Object Type:
Report
System:
The UNT Digital Library
Crystallography of Some of the Transition Element Beryllides
A crystallographic study of the transition element beryllides was undertaken in support of phase diagram work. These beryllides are very high melting, and the use of ordinary methods make it difficult to determine stoichiometry. We have succeeded in establishing the compositions and complete crystal structure description of all of the room temperature stable or metastable compounds of the beryllides of niobium, tantalum, titanium zirconium, hafnium, vanadium, chromium and molybdenum. Since some of the structures found were not previously reported, complete structure determinations had to be done.
Date:
May 24, 1960
Creator:
Zalkin, Allan, 1926- & Sands, Donald, 1929-
Object Type:
Report
System:
The UNT Digital Library
Note on the Numerical Evaluation of Integrals of the Form [integral] [superscript infinity] [subscript infinity] f(x) [golden ratio constant] (x) dx, with Particular Reference to the Determiniation of the Expectation of a Function of a Normally Distributed Random Variable
Abstract: A method is given for the rapid and accurate numerical integration of integrals of the form [integral] [superscript infinity] [subscript infinity] f(x) [golden ratio constant] (x) dx, where f(x) is "smooth."
Date:
May 24, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water
Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage of fuel elements apart from reactors.
Date:
May 24, 1960
Creator:
Clayton, E.D.
Object Type:
Report
System:
The UNT Digital Library
Some Potential Uses of Nuclear Explosives in the Conservation and Development of Water Resources
Abstract. The peacetime application of nuclear explosives to the conservation and development of our national water resources is, at this time, of sufficient promise to present some of the possibilities publicly. In nuclear explosives man has at his disposal and service, a powerful source of energy - a new tool - that we believe can be utilized safely to excavate channels and lake basins, or to create conduits of broken permeable material and underground reservoirs. In surveying the possible applications of nuclear explosives, the following ideas are among those worthy of serious consideration: (a) the use of nuclear explosives for the economic movement of large volumes of earth in the construction of earth fill dames, (b) the use of nuclear explosives for the diversion of a stream from a river system, whose flow is largely lost to the sea, into another stream channel leading to an arid section or a closed basin, (c) the use of nuclear explosives to create a recharge basin or a conduit to a subsurface aquifer for fresh water recharge, and (d) the use of nuclear explosives to create off-channel reservoirs for the elimination of saline waters through recharge to a mineralized aquifer and by evaporation.
Date:
May 24, 1960
Creator:
{{{name}}}
Object Type:
Report
System:
The UNT Digital Library
Analysis of Six-Bar Linkage Using Digital Computer
Summary. The analysis of the motion of a six-bar linkage is difficult because of the large number of variables involved and the large number of calculations that have to be made for each position of the linkage. If a digital computer is used to make the calculations required for a multi-position analysis of a mechanism, it is feasible to design by analyzing a large numbers of similar linkages and selecting the optimum configuration. In this paper expressions have been derived for the output angle as a function of the input angle and the transmission angle as a function of the input angle for any single-degree-of-freedom six-bar linkage for which the parameters are known An example showing the usefulness of a six-bar computer program as a mechanism design tool is discussed.
Date:
May 20, 1960
Creator:
Dunk, A. C. & Hanson, C. L.
Object Type:
Report
System:
The UNT Digital Library
Bibliography on Molecular and Crystal Structure Models
Report that briefly describes many of the models of crystal and molecular structures which have appeared in the literature, and presents a bibliography of the publications, grouped according to model types, which describe the models in more detail.
Date:
May 20, 1960
Creator:
Smith, Deane K.
Object Type:
Report
System:
The UNT Digital Library
Calibration of Line Standards of Length and Measuring Tapes at the National Bureau of Standards
From Abstract: "The methods used at the National Bureau of Standards in calibrating line standards of length and measuring tapes submitted for standardization are outlined. The equipment used is described briefly. There is a discussion of some considerations that should be given as to whether or not a standard should be submitted to the Bureau."
Date:
May 20, 1960
Creator:
Judson, Lewis V.
Object Type:
Report
System:
The UNT Digital Library
Mercury Barometers and Manometers
From Abstract: "Sources of error in measuring pressures are described in considerable detail, particularly for portable instruments including scale, temperature , gravity, capillarity, vacuum errors and return gas column. Methods of minimizing those errors and of making the corrections, including extensive tables, are presented."
Date:
May 20, 1960
Creator:
Brombacher, W. G.; Johnson, D. P. & Cross, J. L.
Object Type:
Report
System:
The UNT Digital Library
L/R Indicator
The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date:
May 20, 1960
Creator:
Minor, G. C.
Object Type:
Report
System:
The UNT Digital Library
The Reduction Of Boolean Truth Functions To Minimal Form
The problem of the reduction of an arbitrary truth function to the minimal union of basic cells is discussed. The solution to this problem has applications to pattern recognition and logical circuit design. An algorithm is presented that solves the problem and generates the class of minimal unions. It partitions an arbitrary truth function into a well-defined set of subfunctions (components) in such a way that the partition is invariant under all transformations that preserve the topology of the original truth function.
Date:
May 20, 1960
Creator:
Natapoff, Alan
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790
This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date:
May 19, 1960
Creator:
Cooper, V. R.
Object Type:
Report
System:
The UNT Digital Library
The Separation of Cerium from the Trivalent Rare Earths Using Hydrogen Peroxide and Sodium Acetate
At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constituents of the waste, and from most of the fission products. The cerium and the trivalent rare earths must then be separated from each other. In the case of cerium recovery, it is necessary to remove the trivalent rare earths in order to maximize the specific activity of the cerium. If promethium is the desired product, a preliminary cerium separation is desirable to protect the ion-exchange resin (used for separating promethium from its adjacent rare earths) from the intense high-energy radiation from cerium.
Date:
May 18, 1960
Creator:
Wheelwright, E. J. & Howard, N. C.
Object Type:
Report
System:
The UNT Digital Library
A Spectrometer for Study of Neutron Activation of Beryllium-7 as a Function of Energy
Abstract. A neutron diffraction crystal spectrometer with a resolution of 13 microseconds per meter and monochromatic beam intensity up to 10(4)n/cm(2)=sec in the range 0.012-0.400 ev has been constructed for study of the activation cross section of Be7 as a function of energy in the thermal region. First preliminary results using ZnS(Ag) as a detector suggest the possibility of a resonance for the Be7(n,p)Li7 reaction in the region of 0.025-0.050 ev.
Date:
May 18, 1960
Creator:
Boyer, Walton T., Jr.
Object Type:
Report
System:
The UNT Digital Library
The ML-1 Design Report
From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date:
May 16, 1960
Creator:
Linenberger, G. A.
Object Type:
Report
System:
The UNT Digital Library