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  Partner: UNT Libraries Government Documents Department
 Collection: Technical Report Archive and Image Library
Tracheobronchial Geometry: Human, Dog, Rat, Hamster - A Compilation of Selected Data from the Project Respiratory Tract Deposition Models
From abstract: "This report documents data collected by detailed measurements of the geometrical features of the tracheobronchial conducting airways of the lungs of four mammalian species." digital.library.unt.edu/ark:/67531/metadc100754/
Fast Neutron Data
A report concerning fast neutrons including theory and compiled data. digital.library.unt.edu/ark:/67531/metadc100798/
Final Engineering Report Covering Austin Beta-Gamma Hand and Foot Checker
Abstract: "This final report discusses the project objectives and the manner in which these were attained in connection with the design and manufacture of the Austin Beta-Gamma Hand and Foot checker (Fig 1). Improvements incorporated to conform the equipment to modern production methods, as well as practical changes to achieve automatic operation and increased stability and to facilitate and simplify maintenance procedures, are covered in detail. The report also includes photographs (Figs. 2 and 3) and a schematic diagram of the final product (Fig. 4)" (p. 1) digital.library.unt.edu/ark:/67531/metadc100764/
Determination of the Number of Double Bonds in Less-Than-Milligram Amounts of Unsaturated Fatty Acids by Catalytic Hydrogenation in the Warburg Apparatus
Report discussing the determination of the number of olefinic double bonds in less-than-milligram amounts of unsaturated fatty acid derivatives using Barcroft-Warburg tissue respirometer as a manometric microhydrogenation apparatus. digital.library.unt.edu/ark:/67531/metadc100763/
Conceptual Design Study of a One Million Gallon Per Day MSM Desalination Plant-Replacement for Demonstration Plant No. 2 at Point Loma, San Diego, California
From foreward: "This is another of a series of reports designed to present accounts of progress on saline water conversion with the expectation that the exhange of such data will contribute to the long range development of economical processes applicable to large scale desalination plants for conversion of sea and other saline waters." This particular report describes various aspects of a demonstration plant in San Diego, California. digital.library.unt.edu/ark:/67531/metadc100759/
Activities of the NBS Spectrochemical Analysis Section: July 1970 to June 1971
Review of the progress in research, instrumentation, and service activities of the Spectrochemical Analysis Section from July 1970 to June 1971. digital.library.unt.edu/ark:/67531/metadc100721/
Vapor Compression Distillation using Secondary Heat Transfer Media
Report discussing a particular method of converting saline water through vapor compression distillation at plants of different sizes. From Introduction: "This report is divided into three Sections (Books) each with its own index. Books I and II contain process and economic data for a 50,000 gpd pilot plant and a 10,000,000 gpd production plant. Book III contains process and economic data for high and low temperature units of 1,000,000 gpd size." digital.library.unt.edu/ark:/67531/metadc100760/
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.12 Alumel-Chromel Cryogenic Thermocouple
This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences. digital.library.unt.edu/ark:/67531/metadc100377/
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples
This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences. digital.library.unt.edu/ark:/67531/metadc100368/
Nuclear Chemical Research, Radiochemical Separations and Activation Analysis: Progress Report 7, November 1957 - October 1958
Progress report discussing projects and work completed by the University of Michigan Department of Chemistry 1957-1958. digital.library.unt.edu/ark:/67531/metadc100784/
The Economics of Desalting Brackish Waters for Regional, Municipal and Industrial Water Supply in West Texas
"This report presents the results of a study of the preliminary feasibility and economics of desalting brackish waters for municipal and industrial watter supply in candidate regions of West Texas" (p. ii). digital.library.unt.edu/ark:/67531/metadc100756/
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Summary Report, July 1959 - September 1961
Summary report discussing progress on the Fast Ceramic Reactor Development Program, a project to develop fast reactors employing ceramic fuels, especially mixed plutonium-uranium oxide. digital.library.unt.edu/ark:/67531/metadc101065/
Southwest Experimental Fast Oxide Reactor Development Program: First Quarterly Report, April-June 1964
From abstract: "This report summarizes the work performed on the Research and Development Program for the Southwest Experimental Fast Oxide Reactor." digital.library.unt.edu/ark:/67531/metadc101096/
Data Book: Physical Properties and Flow Characteristics of Air
Data book to used as an aid in calculations on physical properties and flow characteristics of air. digital.library.unt.edu/ark:/67531/metadc101097/
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1). digital.library.unt.edu/ark:/67531/metadc101070/
EVESR Nuclear Superheat Fuel Development Project: Second Quarterly Report, September-November 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project. digital.library.unt.edu/ark:/67531/metadc101081/
The Legendary "White Metal" and its "Ore"
Report concerning stories about claims of a "white metal" extracted from an "ore" found packed around pieces of iron or steel. It includes information about various tests conducted about the validity of these claims and their findings. digital.library.unt.edu/ark:/67531/metadc100837/
Thermodynamic Properties of Forsterite and Serpentine
From introduction: "This report contains the results of measurements to obtain the heats of formation of forsterite and chrysotile; entropies at 298.15 K of two polymorphs of serpentine, chrysotile and antigorite; and high temberature heat content increments for antigorite. These results have been combined with other pertinent data to derive heat and free energy values at high temperatures." digital.library.unt.edu/ark:/67531/metadc100853/
Metal Mine Ventilation and its Relation to Safety and Efficiency in Mining Operations
Report on mine ventilation and its relation to safety and efficiency. digital.library.unt.edu/ark:/67531/metadc100846/
Recovery of Gold from Black Sand Tailings
Report on the recovery of gold from black sand tailings, based on tests conducted at the U.S. Bureau of Mines' Alaska Station. digital.library.unt.edu/ark:/67531/metadc100847/
Future Timber Supply for Coal Mines: What One Company is Doing
Report discussing a case study of a coal company in Western Pennsylvania to show how mining companies might decrease their timber bills. digital.library.unt.edu/ark:/67531/metadc100851/
The Recovery of Unburned Fuel from Boiler Furnace Refuse
Report on recovering unburned fuel from boiler furnace refuse, based on processes used in Europe and tests in the United States. digital.library.unt.edu/ark:/67531/metadc100848/
Carbon Tetrachloride Extinguisher of Electric Fires
Report discussing "the extent and nature of the hazards to firefighters from gases and smoke resulting from the application of carbon tetrachloride extinguisher to electric arcs, burning insulation or fires such as may occur in electrical apparatus and machinery. The experiments described were made for the purpose of determining the nature of gases and smoke and ascertaining their toxic properties" (p. 1). digital.library.unt.edu/ark:/67531/metadc100850/
What is Known about the Effect of Smoke on Health
From title page: "For some years the Bureau of Mines, in connection with its investigations relating to efficiency in the combustion of fuels, as been engaged in a study of smoke prevention. Popular support for such work is usually based upon the injurious effects of smoke on the human ssytem, and this paper is published as a contribution to the literature dealing with that subject." digital.library.unt.edu/ark:/67531/metadc100852/
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1971 - December 1, 1971, Appendix
Report documenting radioactive fallout across the world, including material in the atmosphere, on land, and that has deposited into food and water supplies. digital.library.unt.edu/ark:/67531/metadc100817/
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities. digital.library.unt.edu/ark:/67531/metadc101085/
Steam-Cooled Power Reactor Evaluation for 300 MW(e) Separate Superheater Reactor
From introduction: "This report provides the preliminary design for the nuclear portion of a 300 MWe Boiling Water Separate Superheater Plant to be in operation by 1967." digital.library.unt.edu/ark:/67531/metadc101056/
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 2
Second volume of a compilation of information about reactor containment, written by experts from a variety of organizations. digital.library.unt.edu/ark:/67531/metadc101034/
EVESR Nuclear Superheat Fuel Development Project: Third Quarterly Report, December 1962-February 1963
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project. digital.library.unt.edu/ark:/67531/metadc101072/
Runaway Analysis for a Gas Cooled Reactor
From abstract: "This report presents an IBM digital computer program that solves numerically and simultaneously the equations that describe gross reactor behavior under runaway conditions." digital.library.unt.edu/ark:/67531/metadc101098/
First Annual Report - Operation of the Multi-Effect Multi-Stage Flash Distillation Plant (Clair Engle), San Diego, California
Annual report discussing the activities and operation of the Senator Clair Engle Plant (CEP), a multi-effect multi-stage flash (MEMS) distillation plant for converting sea water, located in San Diego, California. digital.library.unt.edu/ark:/67531/metadc100757/
Observation of Taylor Instability in Gases
Report discussing experiments related to Taylor instability in an all gaseous system. Experimental methods, apparatuses, and conclusions are described. digital.library.unt.edu/ark:/67531/metadc100936/
Electronic Devices for Nuclear Physics Quarterly Report: Number 19, February 1, 1955 - April 30, 1955
Report regarding the ongoing development of both multi-alkali photocathodes and improved photomultipliers. digital.library.unt.edu/ark:/67531/metadc100937/
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958
Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment. digital.library.unt.edu/ark:/67531/metadc100984/
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. digital.library.unt.edu/ark:/67531/metadc100942/
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: May 1957 - September 1957
Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment. digital.library.unt.edu/ark:/67531/metadc100983/
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i). digital.library.unt.edu/ark:/67531/metadc100943/
Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964
From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels." digital.library.unt.edu/ark:/67531/metadc100982/
The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium
Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information. digital.library.unt.edu/ark:/67531/metadc100940/
An Improved 8 and 32 Inch Diffusion Pump Combination
Report describing the design and performance of an 8 inch and 32 inch diffusion pump and measurements of their capacity. digital.library.unt.edu/ark:/67531/metadc100932/
Phase 3 Design Analysis for the Army Package Power Reactor: Volume 1 (Design Analysis)
From foreword: "This report consists of two volumes which comprise the Phase III Design Analysis for the Army Package Power Reactor." The first volume discusses design analysis of the reactor. digital.library.unt.edu/ark:/67531/metadc100960/
High Power Density Development Project: Third Quarterly Progress Report, October - December, 1960
From introduction: "Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC." digital.library.unt.edu/ark:/67531/metadc101058/
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1). digital.library.unt.edu/ark:/67531/metadc101069/
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1). digital.library.unt.edu/ark:/67531/metadc101073/
Preliminary Design: 22,000 SHP Boiling Water Reactor Marine Propulsion Plant for a Commercial Tanker
From abstract: "A preliminary design is presented for a boiling water reactor power plant for a propulsion of a 22,000 SHP commercial tanker." digital.library.unt.edu/ark:/67531/metadc101038/
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities. digital.library.unt.edu/ark:/67531/metadc101084/
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project. digital.library.unt.edu/ark:/67531/metadc101080/
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1). digital.library.unt.edu/ark:/67531/metadc101071/
Heat Transfer Reactor Experiment Number 3: Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program
From abstract: "Describes Heat Transfer Reactor Experiment No. 3, a solid-moderated nuclear power plant with a horizontal reactor." digital.library.unt.edu/ark:/67531/metadc101099/
International Symposium on Developments in Irradiation Capsule Technology: Held at Pleasanton, California, May 3-5, 1966
Assembled papers regarding advances in irradiation capsule technology. digital.library.unt.edu/ark:/67531/metadc172550/
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