Thorium Isotopes Method for Dating Marine Sediments (open access)

Thorium Isotopes Method for Dating Marine Sediments

This thesis is concerned with a possible method of improving the well-known ionium method of age determination of deep-sea sediment sections (Pet-53, Zou-58, Kul-55, Ran-54) both with respect to accuracy of individual determinations and with respect to the range of applicability of the method.
Date: May 31, 1960
Creator: Almodóvar, Ismael
System: The UNT Digital Library
Cosmogenic Carbon-14 and Chlorine-36 in Meteorites (open access)

Cosmogenic Carbon-14 and Chlorine-36 in Meteorites

In 1947 Bauer, and later independently Huntley (1948), pointed out that the helium content of iron meteorites as measured by Paneth and coworkers could be accounted for by the accumulation through cosmic-ray production rather then the decay of uranium and thorium. Bauer (1947) also predicted that the meteroitic helium should contain a significant proportion of He3. I was realized that by studying the effects of cosmic radiation on meteorites much could be learned about the history of meteorite and cosmic radiation. Chemical and instrumental techniques have been developed for the isolation, purification, and measurement of cosmic-ray-induced C14 in both stone and iron meteorites. The isolation of carbon from the silicate materials is done by fusion in an oxidizing flux in a vacuum system. From the iron meteorites the carbon is recovered by the decomposition of the metal in nitric acid in a closed system.
Date: June 4, 1962
Creator: Goel, Parmatma S.
System: The UNT Digital Library
A Multi-Channel Unit of Solid State Counters for Nuclear Spectroscopy (open access)

A Multi-Channel Unit of Solid State Counters for Nuclear Spectroscopy

A matrix of twenty 2 x 12 mm squared surface barrier counters has been constructed for use in the image plane of a magnetic spectrometer. The outputs of individual crystals are displayed in predetermined channels of a 100-channel pulse height analyzer. This is done by connecting separate crystals to succession sections of a delay line and converting the time difference between signals arriving at the ends of the line into pulse heights. Simple procedures for producing reliable Ge-Au surface barriers and contacts and certain properties of such counters are discussed. A sample of information decoded by this unit is presented.
Date: May 20, 1960
Creator: Bilaniuk, O. M.; Hamann, A. K. & Marsh, B. B.
System: The UNT Digital Library
A Systematic Study of (p,xp) Reactions in the 100-400 MEV Region (open access)

A Systematic Study of (p,xp) Reactions in the 100-400 MEV Region

(p,xp) reactions are those nuclear reactions induced by high energy protons in which both the mans and the charge of the target nucleus are reduced by x-1 units. The most common type of these reactions to be expected in the 100 to 400 Mev region involves the exclusive emission of protons as a results of the interactions. The specific (p,xp) reactions investigated in this study were those where 2 is less than or equal to x where x is less than or equal to 5.
Date: June 2, 1961
Creator: Morrison, David Lee
System: The UNT Digital Library
Thalluim in Meteorites (open access)

Thalluim in Meteorites

Procedures for the separation and concentration of microgram to nanogram amounts of thallium from gram amounts to galena and meteorite metal, sulfide, and silicate phases were developed and are described. The thallium is extracted from aqueous bromide of chloride solutions of moderate acidity using diethyl ether. A device for elimination of the large volumes of solvent by dropwise evaporation is described. Organic matter in the residue is destroyed by treatment with aqua regia, and the thallium is the residue is converted to the nitrate for spectrochemical or mass-spectrometric examination. The presence of thallium in the residue is tested by Rhodamine B. test.
Date: December 20, 1960
Creator: El-Badry, Hamed M.; Hodge, Edwin S.; Baer, William K. & Kohman, Truman Paul, 1916-
System: The UNT Digital Library
Computer description APPR-1 simulator (open access)

Computer description APPR-1 simulator

The APPR-1 is a pressurized water reactor having a low specific heat fuel and a water primary coolant. The primary coolant loop delivers heat from the reactor to the steam generator. The secondary water in the steam generator is converted to steam and then taken to the turbine to drive an electrical generator. The simulation of this system is broken down into three primary areas: the neutron kinetics in the reactor which are necessary to generate the primary power function, the heat transfer in the reactor, and the heat transfer in the steam generator.
Date: December 15, 1958
Creator: RCA Service Company
System: The UNT Digital Library
An approach to the study of solid state bonding (open access)

An approach to the study of solid state bonding

The program objective has been to investigate the possible similarity between a bond interface and a grain boundary. The criterion for establishing the similarity of a bond interface and a grain boundary was the migration characteristics of the boundary under the influence of controlled orientation, strain level, temperature and time. In addition, the orientation dependency of the "threshold", or minimum deformation, for bonding would have to be determined. The initial bonding studies were to be made by a "cold welding" technique; subsequently, elevated temperatures bonding would have been attempted. Migration of boundaries was to be observed by high temperature metallographic techniques.
Date: 1959
Creator: Steele, R. K. & Kozol, J.
System: The UNT Digital Library
Bremestrahlung in p-p-Collisions at an Energy of 150 MeV (open access)

Bremestrahlung in p-p-Collisions at an Energy of 150 MeV

The differential cross-section for bremestrahlung in p-p collisions at an energy of 140 Mev is calculated at the upper end of the photon spectrum. the only transition which is considered is the E2 transition between 1D2 and the 1S0 state. The Siegart theorem is used and influence of the Coulomb force between the two protons is neglected.
Date: 1960
Creator: Dullemond, C. & de Swart, J. J.
System: The UNT Digital Library
A Theoretical and Experimental Study of Optical Fibers (open access)

A Theoretical and Experimental Study of Optical Fibers

A geometrical treatment has been used to outline the theoretical properties of optical fibers which are imperfect as well as geometrically and optically perfect. Experiments have been performed to measure some to the optical properties of individual fibers and fiber bundles.
Date: April 1, 1960
Creator: Potter, Robert J.
System: The UNT Digital Library
Self Casting of Nuclear Fuel Elements, Report No. II (open access)

Self Casting of Nuclear Fuel Elements, Report No. II

Room temperature tensile properties are given for a series of slip cast APPR-type UO2 stainless steel fuel plates. Properties of conventionally fabricated type SM-1 dispersion plates were determined for comparison. Slip cast fuel plates sintered to 90% density, hot or cold rolled approximately 30% and annealed 1 hour at 1120% showed ultimate tensile strengths equal to those of the conventional plates, slightly lower yield strengths, and tripled ductility.
Date: unknown
Creator: Comstock, Gregory J.; Clark, Frances N.; Baron, Edward N.; Guendel, Henry W. & Wilson, Edmund B.
System: The UNT Digital Library
First Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization (open access)

First Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization

The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Date: June 1, 1960
Creator: Isotopes Incorporated
System: The UNT Digital Library
Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization (open access)

Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization

The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Date: September 15, 1960
Creator: Isotopes Incorporated
System: The UNT Digital Library
The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization (open access)

The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization

The study which has been carried out under Contract AT(30-1)2477 has as its objective the review of all work which has been done on the application of radionuclear techniques to research in water resources and supply, the evaluation of this work, and the suggestions of specific experiments which must be performed if these applications are to be extended.
Date: January 31, 1961
Creator: Feely, Herbert W., 1928-
System: The UNT Digital Library
Diffusion of Fission Gases Through Uranium Oxide and Uranium Carbide (open access)

Diffusion of Fission Gases Through Uranium Oxide and Uranium Carbide

A program has begun embodying a study of the diffusion rates of krypton and xenon into unirradiated UO2 and UC at temperatures between 1000°C and 2500°C.The experimental technique is described in some detail, involving exposure of UO2 and UC samples to a Kr85 atmosphere at various temperatures, removal of surface-adsorbed krypton, dissolution of the sample, collection and ion chamber measurement of the diffused Kr, and calculation of diffusion coefficients from these data.
Date: August 11, 1960
Creator: Weinstock, J. J.
System: The UNT Digital Library
Diffusion of Krypton Through Uranium Carbide - Final Report (open access)

Diffusion of Krypton Through Uranium Carbide - Final Report

This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
Date: January 10, 1961
Creator: Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.
System: The UNT Digital Library
Final Report on the Design, Construction and Operation of a Pulsed Subcritical Uranium Assembly for Eduational Uses (open access)

Final Report on the Design, Construction and Operation of a Pulsed Subcritical Uranium Assembly for Eduational Uses

This report describes the design, construction and operation of a sub-critical nuclear reactor, intended for college teaching of reactor physics and of nuclear phenomena.
Date: December 31, 1959
Creator: Rensselaer Polytechnic Institute
System: The UNT Digital Library
Fuel Element Development Program for the Pebble Bed Reactor (open access)

Fuel Element Development Program for the Pebble Bed Reactor

...Development during this quarter have caused a shift in emphasis of the Pebble Bed Reactor Fuel Element Development Program from coatings on the sphere surface to coatings on individual fuel particles as the major deterrent to fission product leakage. In a high level irradiation test, cracks developed in the coatings of specimens coated with pyrolytic carbon and siliconized silicon carbide. In another high level irradiation test, a graphite sphere fueled with Al2O3 coated with UO2 particles is showing excellent fission product retention. The leakage factors (i.e. rate of release/rate of production) for long lived volatile fission products such as Kr85m, Kr87, Kr88, Xe133, Xe135 are ranging from 10 to the negative 9th to 10 to the negative 6th. If this degree of fission product retention is maintained in a large power reactor, it would result in essentially a "clean" primary loop.
Date: 1960
Creator: Sanderson & Porter, Inc.
System: The UNT Digital Library
Thorium Oxide Infiltration of Graphite Spheres (open access)

Thorium Oxide Infiltration of Graphite Spheres

Work on the preparation of graphite spheres containing thorium oxide for use as breeder elements in the Pebble Bed Reactor-Steam Power Plant is described. Graphite spheres of varying density were infiltrated with thorium nitrate solutions, followed by denitration to thorium oxide.
Date: June 15, 1960
Creator: Parker, W. E. & Rusinko, F.
System: The UNT Digital Library
Fuel Element Development Program for the Pebble Bed Reactor (open access)

Fuel Element Development Program for the Pebble Bed Reactor

Previous results from the Pebble Bed Reactor Fuel Element Development Program had shown the excellent promise of vapor-deposited Al2O3 doq5intw on UO2 particles as a low permeability high temperature fission product barrier. However, since the matrix material for the PBR fuel element is a graphite sphere, carbonaceous coatings on the dispersed fuel particles might be of more interest because of improved particle coating-matrix compatibility and no displacement of neutron moderating materials. Since a pyrolytic carbon coating also appeared to be low permeability higt temperature material, emphasis was placed on the development of pyrolytic carbon coated UC2 particles dispersed in a graphite sphere as the reference PBR fuel element.
Date: 1961
Creator: Sanderson & Porter, Inc.
System: The UNT Digital Library
The Pebble Bed Reactor Program (open access)

The Pebble Bed Reactor Program

Several different types of experimental facilities have been evaluated to determine the most suitable and economical means of demonstrating the technical feasibility of the Pebble Bed Reactor concept. The criteria for demonstrating technical feasibility are: 1) bulk irradiation of fuel elements in order to obtain statistical data on performance, 2) Maintenance of system activity at specified levels, and 3) Feasible maintenance procedures. An additional criterion, which is required to achieve breeding in the full scale plant is - 4) Demonstrate the mechanics of continuous refueling under load.
Date: 1959
Creator: Sanderson & Porter, Inc
System: The UNT Digital Library
The Pebble Bed Reactor Program (open access)

The Pebble Bed Reactor Program

The coolant stream of all nuclear reactors caries some activity due to one or more of the following: a) neutron activation of coolant atoms, b) neutron activation of corrosion products carried by the coolant stream, c) fission recoil into the coolant stream, d) fission products leaking into the coolant stream. The Pebble Bed Reactor is not concerned with (1) and (b) since the helium working fluid, or coolant, has an activation cross-section which is essentially zero and its inert chemical nature effectively eliminates corrosion as a consideration. We are not concerned with (c) since developments to date, of fuel and particle coatings to reduce fission product leakage, will also prevent fission recoil into the coolant stream.
Date: 1960
Creator: Sanderson & Porter, Inc.
System: The UNT Digital Library
Pebble Bed Friction Factor and Thermal Expansion Tests (open access)

Pebble Bed Friction Factor and Thermal Expansion Tests

Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
System: The UNT Digital Library
PBM, A Two-Group, Two-Region Reactor Model for Homogeneous, Highly Absorbing Systems and Machine Codes for Its Application (open access)

PBM, A Two-Group, Two-Region Reactor Model for Homogeneous, Highly Absorbing Systems and Machine Codes for Its Application

A nuclear model has been developed for homogeneous, two-region reactors possessing a relatively large percentage of epithermal absorption in both the core and blanket region. A number of new IBM 650 programs have been developed and existing programs modified to form a group of programs, compatible with the nuclear model and with each other, which can be used for preliminary evaluation of the effed of design variable on reactor characteristics.
Date: December 1960
Creator: Sanderson & Porter, Inc.
System: The UNT Digital Library
Coolball, a Machine Code for Thermal Analysis of Pebble Bed Reactor Cores (open access)

Coolball, a Machine Code for Thermal Analysis of Pebble Bed Reactor Cores

COOLBALL is an IBM 650 machine program designed to calculate local gas and ball temperatures, gas flow, and pressure loses as induced by non-uniform power generation and voidage within an axial flow Pebble Bed Reactor core. This code has been used extensively to study the thermal characteristics of Pebble Bed Reactor cores in support of a broad program for the development of the PBR concept.
Date: 1961?
Creator: unknown
System: The UNT Digital Library