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Conceptual Design Study of a Mobile Gamma Irradiator for Fruit Produce
From introduction: This report covers the results of a study of a mobile irradiator for fruit grown in California.
Date:
May 31, 1962
Creator:
Associated Nucleonics (Garden City, N.Y.)
Object Type:
Report
System:
The UNT Digital Library
A Conceptual Study of a 100 kw Gas Cooled Reactor Power Plant for a Remote Location
From introduction: This report details the conceptual design of a 100 kw gas cooled reactor power plant of the type that would satisfy the electrical and space heating load of the Air Force distant early warning stations and might find application at other remote bases.
Date:
May 31, 1955
Creator:
Frankfort, J. H. & Thompson, W. I.
Object Type:
Report
System:
The UNT Digital Library
The Conversion of UF4 to U3Os
Methods of conversion of UF4 to U3O8 by fusion with ammonium oxalate dihydrate and other salts are described.
Date:
May 28, 1941
Creator:
Tevebaugh, A. D.; Tevebaugh, R. D.; Cline, W. D. & Warf, James C.
Object Type:
Report
System:
The UNT Digital Library
The Coprecipitation of Thorium and Uranium Peroxides
From abstract: "Experiments covering the coprecipitation of Thorium and Uranium peroxides are described on synthetic and actual 1300 cycle machine wash effluents."
Date:
May 10, 1946
Creator:
Oringer, Roy; Woodard, R. W. & Larson, C. E.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date:
May 1963
Creator:
Larrick, A. P.
Object Type:
Report
System:
The UNT Digital Library
Counting Room Equipment and Procedures and Sample Preparation
The following are some of the equipment currently used in the Health Physics counting rooms at the Laboratory: scintillation counters, end window beta-gamma counters, precipitcon beta-gamma counter, autoscaler beta-gamma counter, and continuous flow proportional counter. This technical report describes the equipment, supporting equipment, procedures, and sample preparation in use at the Laboratory.
Date:
May 1954
Creator:
Weiss, M. M. & Marshall, J. B.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant
From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date:
May 5, 1952
Creator:
Wood, H. P.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of Portable Instruments
The decontamination of portable instruments by the Calibration Unit has presented a problem for some time. Most of the contamination is in the 100 to 500 c/m or 500 to 2000 d/m range. Higher levels of contamination can usually be reduced to these levels, but further cleaning proves quite difficult
Date:
May 22, 1953
Creator:
Unruh, C. M.
Object Type:
Report
System:
The UNT Digital Library
The Deposition of Plutonium and Certain Fission Products in Bone as a Decontamination Problem
The following report discusses the deposition of radioactive elements during a nuclear fission in the skeleton. Studies are concerned with chronic effects of toxic radiation developing within the bone marrow and decontaminating the cells.
Date:
May 15, 1946
Creator:
Copp, D. Harold; Greenberg, David M. & Hamilton, Joseph G.
Object Type:
Report
System:
The UNT Digital Library
Description of Method for Determining Geometric Parameters of Surfaces in Contact
"A method and equipment are described for determining the surface parameters of contact required for heat transfer calculations. In this method, the output of a surface analyzer for one surface is recorded on one channel of magnetic tape and the output for the other surface of the contact pair on a second channel. The tape is played back to an analog computer which then integrates the analog voltage to compute the void volume thickness, the number of contact points, and the ratio of metallic contact area to the total area."
Date:
May 2, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Description of Purex Plant Process
Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date:
May 19, 1959
Creator:
Irish, E. R.
Object Type:
Report
System:
The UNT Digital Library
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant
Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date:
May 1, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Date:
May 15, 1958
Creator:
Morrow, G. W.
Object Type:
Report
System:
The UNT Digital Library
Design and Properties of a Neon Filled Spark Chamber in a Magnetic Field
Introduction: Recently a new type of charged particle detector, the so-called spark chamber, has been developed. The detector has certain advantages in high energy physics over bubble chambers aside from its much lower cost.
Date:
May 1, 1961
Creator:
Heyn, Maarten P.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4
Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.
Date:
May 1, 1962
Creator:
Jenks, G. H.
Object Type:
Report
System:
The UNT Digital Library
Determination of Uranium by Fluorescence
Abstract: "The uranium content of badly contaminated uranium solutions may be determined quickly using visual comparison methods to an accuracy of [...]. This accuracy may be considerably improved by employing the fluorimeter herein described. Interfering ions and their removal using liquid-liquid extractions are considered."
Date:
May 28, 1948
Creator:
Grimes, W. R. & Clark, F. E.
Object Type:
Report
System:
The UNT Digital Library
Development of a Gas Injector System for Homogeneously Labeling Gas Storage Reservoirs
"The laboratory experiments and field testing which were carried out in the development of a homogeneous gas labeling device are described. Detailed drawings of the injector and its most critical components are included. Recommendations are made for a production model of the device along with estimated costs of construction."
Date:
May 1, 1961
Creator:
Sewell, Curtis & Schulz, Isidor
Object Type:
Report
System:
The UNT Digital Library
The Development of a Melting Method for Conversion of Zirconium Sponge to Corrosion Resistant Ingot
This report covers an investigation meant to find the feasibility of producing corrosion resistant zirconium from sponge by special melting techniques. The zirconium metal has certain required specifications, such as: the metal must be free from bafnium, and it must be free from other impurities of undesirable neutron cross section.
Date:
May 4, 1950
Creator:
National Research Corporation (U.S.)
Object Type:
Report
System:
The UNT Digital Library
Development of Equipment for the Purification of Mercury by Distillation
Abstract: "An investigation of the mercury salvage program has resulted in the development of an improved high compacity type of distillation apparatus. The still, electrically heated and essentially automatic in its operation, will produce at a rate greater than 75 pounds per hour and develop a product 99.99% pure or better. This still will handle the lowest grade crude of amalgam that can pass through the feed lines and will continue to develop a pure prodcut for comparatively long periods of time. The clean-out operation is amazingly simple and convenient and may be done within one-half hour while the apparatus itself is still hot. Two models of this design are scheduled for installation in a mercury recovery room of the Alpha Analytical Department of Building No. 9207."
Date:
May 26, 1945
Creator:
Lee, J. E. & Susano, C. D.
Object Type:
Report
System:
The UNT Digital Library
Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963
Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
Date:
May 13, 1963
Creator:
Garelis, Edward & Meyer, Paul
Object Type:
Report
System:
The UNT Digital Library
Development of Techniques for Power Production From Mixed Fission Products
"Progress is reported on Phase II of a program for the development of a mixed fission product fueled thermoelectric generator. Materials studies are described in which bonded assemblies of bismuth telluride were life tested up to 3000 hours at 350 to 400 deg F hot junction temperature. Data were too inconsistent to define any satisfactory long-life bonding process. Further work is needed to eliminate the process variables. Insulation studies aimed at determining the thermal conductivity of various insulations with different fill gases under reduced pressures are described. Opacified aerogel powder appears to be very promising as an insulation medium for a diffuse heat source. A full- scale simulated test generator aimed at proving out the concept of a diffuse heat source for power generation is described. Progress on the construction of this electrically heated generator and its thermoelectric power converter is related.
Date:
May 21, 1962
Creator:
Lemanski, E. J.
Object Type:
Report
System:
The UNT Digital Library
Development of the Flow Sheet for Incinerating Contaminated Combustible Waste: Engineering Research Final Report
From introduction: This report serves as a recommendation that a full-scale incineration process be installed at Mound Laboratory and provides a complete flow sheet for this process and recommended designs for the critical parts of the processing equipment. It contains justification for the process, a history of the investigation including early work and pilot plant results, an explanation of the values and information given in the flow sheet, and the reasons for the recommended design features.
Date:
May 15, 1951
Creator:
McEwen, M.; Schauer, P. J. & Aponyi, T.
Object Type:
Report
System:
The UNT Digital Library
Discussion of Quadrupole Precession
From abstract: "In this paper the motion of a nucleus with an intrinsic quadrupole moment in an external electrostatic field gradient is discussed from a classical point of view. It is shown that in the classical approximation the angular momentum may precess about the direction of strongest field gradient or about the direction of intermediate field gradient, but not about the direction of weakest field gradient. The classical precession frequencies are found to be related to the quantum mechanical dipole transition frequencies."
Date:
May 31, 1962
Creator:
Raich, J. C. & Good, R. H. (Roland Hamilton), 1923-
Object Type:
Report
System:
The UNT Digital Library
Distribution of Thermal Neutrons from Fast Sources in Exponential Piles
Report regarding the mathematical analysis of the exponential pile experiment using highly absorbent slugs and assuming the emitting of fast neutrons. Related theory and equations are discussed.
Date:
May 27, 1954
Creator:
Anselone, Philip M.
Object Type:
Report
System:
The UNT Digital Library