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Plastic stress-strain relations for combined tension and compression
No Description Available.
Plastics as structural materials for aircraft
The purpose here is to consider the mechanical characteristics of reinforced phenol-formaldehyde resin as related to its use as structural material for aircraft. Data and graphs that have appeared in the literature are reproduced to illustrate the comparative behavior of plastics and materials commonly used in aircraft construction. Materials are characterized as to density, static strength, modulus of elasticity, resistance to long-time loading, strength under repeated impact, energy absorption, corrosion resistance, and ease of fabrication.
Plate compressive strength of FS-1H magnesium-alloy sheet and a maximum-strength formula for magnesium-alloy and aluminum-alloy formed sections
No Description Available.
Plate method of ground representation for wind-tunnel determination of elevator effectiveness in landing
No Description Available.
Plates 1 Through 62 to Accompany Uranium Favorability of Late Eocene Through Pliocene Rocks of the South Texas Coastal Plain
This is a set of 62 plates that accompany a report on uranium favorability in rocks of the south Texas coastal plain.
Plates To Accompany Final Report Of Geological, Geophysical, Chemical, And Hydrological Investigations Of The Sand Springs Range, Fairview Valley, And Fourmile Flat, Churchill County, Nevada
The following documents are aseries of plates to accompany the final report of "Geological, Geophysical, Chemical, and Hydrological Investigations of the Sand Springs Range, Fairview Valley, and Fourmile Flat, Churchill County, Nevada".
Plating Thickness Tester
An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Platinum Deposits of the Goodnews Bay District, Alaska
From abstract: Platinum placers were discovered in 1926 in a small area south of Goodnews Bay, in southwestern Alaska. Beginning in 1927, the placers were worked for 7 years by small-scale mining methods; in later years dragline excavators and a dredge were utilized. These deposits are important, not only because they are of high grade but because they are the only commercial source of platinum metals in the United States. This report details the deposits in this district.
Platinum Resistance Thermometry
From Introduction: "This monograph describes the calibration of standard platinum resistance thermometers at the NBS including the equipment, techniques, and procedures."
Platinum Resistance Thermometry at High Temperatures
Report issued by the Bureau of Standards over platinum resistance thermometry. The advantages and limitations at high temperatures are discussed. This report includes tables, and illustrations.
Pleasure Boat Loading Related Accident Education
Abstract: This project deals with educational solutions to loading related pleasure boat accidents.
Pliocene Fossils From Limestone in Southern Florida
Abstract: This paper describes the mollusks and echinoids found in limestone dredged from ditches along the Tamiami Trail in southern Florida, in the area mapped as "Lostmans River limestone (Quaternary)" by Sanford but included in the Pliocene Caloosahatchee formation by Cooke and Mossom on the evidence of these fossils as identified by Mansfield. The matrix of the fossils is unlike the typical Caloosahatchee formation, which is sandy, but the fauna is closely related to that of the upper part of the Caloosahatchee formation and is regarded as a facies of the Caloosahatchee. The fauna shows considerable resemblance to that of the Imperial formation of California but may not be contemporaneous with it.
Plowshare Symposium, 1964: Engineering with Nuclear Explosives
From foreword: The major objective of the symposium is informing engineers in industry, military, educational institutions, and in government agencies throughout the world of the current state-of-the-art nuclear explosives from an engineering standpoint.
Plutonium Calorimetry and SNM Holdup Measurements, Progress Report: March 1976-August 1976
The calorimetric instrumentation developed at Argonne National Laboratory (ANL) for making nondestructive measurements of the plutonium content of fuel rods is discussed. Measurements with these instruments are relatively fast (i.e., 15 to 20 minutes) when compared to the several hours usually required with more conventional calorimeters and for this reason are called ''fast-response.'' Most of the discussion concerns the One-Meter and the Four-Meter Fuel-Rod Calorimeters and the Analytical Small-Sample Calorimeter. However, to provide some background and continuity where needed, a small amount of discussion is devoted to the three earlier calorimeters which have been described previously in the literature. A brief review is presented of the literature on plutonium holdup measurements. The use of gamma-ray techniques for holdup measurements is discussed and results are given for the determination of sample thickness using the ratio of intensities of high- and low-energy gamma rays. The measurements cover the plutonium metal thickness range from 0.001 to 0.120 inches. The design of a gamma-ray collimator with 37 parallel holes is also discussed. Neutron-counting experiments using BF3 proportional counters embedded in two polyethylene slabs are described. This detector configuration is characterized for its sensitivity to sample and background plutonium, counting both coincidence (fission) and total neutrons. In addition, the use of infrared imaging devices to measure small temperature differences is considered for locating large amounts of plutonium holdup and also for performing fast attribute checks for fabricated fuel elements.
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Plutonium Recycle Critical Facility: Final Safeguards Analysis
Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements
Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Plutonium Recycle Program Annual Report, Fiscal Year 1958
Report that describes work performed by by the Hanford Laboratories Operation on the Plutonium Recycle Program during the Fiscal Year.
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak
Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis
Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis
This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Plutonium Recycle Test Reactor Final Safeguards Analysis
Report describing the Hanford Plutonium Recycle Test Reactor (PRTR), its building, safety procedures, site, operations, and analyses of its safety features.
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Plutonium Recycle Test Reactor Preliminary Safeguards Analysis
Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.
Plutonium Safety Training Course
This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the trans-plutonium nuclides relative to plutonium-239 follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed.
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959
From abstract: The principal efforts are the furthering of the final design and preparation of specifications for some long-lead components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported.
PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960
From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.
PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960
From abstract: Reactor development work includes: initiation of the flexible zero-power test (PMZ-1) experimental program, fabrication and delivery of a PM-1 type fuel element, continuation of reactor flow and heat transfer tests, development work on rare earth control rods, and testing and redesign of the prototype magnetic jack-type control rod actuator.
PM-1 Nuclear Power Plant Program: 8th Quarterly Progress Report, December 1, 1960 to February 28, 1961
From abstract: The objective is the design, development, fabrication, installation and initial testing and operation of a prepackaged, air-transportable, pressurized water reactor nuclear power plant, the PM-1.
PM-1 Nuclear Power Plant Program: 9th Quarterly Progress Report, March 1, 1961 to May 31, 1961
From abstract: The objective of the contract is the design, development, fabrication, installation initial testing and operation of a prepackaged, air transportable nuclear power plant, the PM-1.
PM-1 Nuclear Power Plant Program: Final Progress Report, September 1, 1962 Through Completion
From abstract: The principal efforts during the final period were concerned with plant testing, modifications to the plant to enable it to produce full design load at high ambient temperatures, the compilation and evaluation of plant performance data, preparation of documents and transfer of the plant to the AEC and final resolution of all outstanding contract scope items.
PM-1 Nuclear Power Plant Program: Plant Performance Studies, Final Periodic Report, September 1, 1962 to December 31, 1962
From abstract: Data obtained during the performance testing of the PM-1 plant was compiled and evaluated. It is concluded from the data that the plant performance in general meets or exceeds specifications. Transient and steady-state electrical fluctuations are well within specified limitations. Heat balance data for both the primary and secondary systems agree reasonably well with design predictions. Radiation levels are below those anticipated.
PM-1 Reactor Core Final Design Report
From introduction: This report presents and evaluates the final design of the reactor core for the PM-1 Nuclear Power Plant. The design criteria required a pressurized water cooled and moderated core with a two-year life at design power and a positive shutdown margin under all conditions with either one control rod stuck completely out or with two control rods stuck in the operating condition.
PM-3A Nuclear Power Plant Program
From summary: Progress report on the production of detailed piping and equipment installation drawings for the PM-3A nuclear power plant program. Attention has been paid to the procurement of those valves and specialty items associated with the piping system.
PM Research and Development Program: 1st Quarterly Progress Report, April 15, 1961 to June 30, 1961
From summary: This report contains a description of the work accomplished during the first project quarter of the PM Research and Development Program, divided into six areas: core design development, plant design development, fuel element and core component development, critical experiments and zero power testing, reactor flow rates, and heat transfer tests.
PM Research and Development Task 1.0 : Core 2 Final Design Report
From summary: This report describes the final design of Core 2, which is being developed primarily as a replacement core for the PM-1 and PM-3A nuclear power plants. In addition, the thermal and hydraulic capabilities were investigated; these indicate applicability of the core to higher powered PM-type plants.
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements
This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
The Pocket Gophers (Genus Thomomys) of Arizona
Distributional study of the pocket gophers of Arizona, including economic status and species and subspecies.
The Podmoskovnaya Underground Coal Gasification Station
From abstract: "Survey of the Soviet effort in underground coal gasification and summarizes research conducted at the Podmoskovnaya Station until its close in 1963."
Point drag and total drag of navy struts no. 1 modified
This report deals with the results of tests on struts conducted at Washington Navy Yard. Two models of the modified Navy strut, no. 1, were tested in the 8 by 8 foot wind tunnel. The tests were made to determine the total resistance end effect and the pressure distribution at various wind-tunnel speeds with the length of the strut transverse to the current. Only the measurements made at zero pitch and yaw are given in this report.
Poisson's ratios and volume changes for plastically orthotropic material
Measurements of Poisson's ratios have been made in three orthogonal directions on aluminum alloy blocks in compression and on stainless-steel sheet in both tension and compression. These measurements, as well as those obtained by density determinations, show that there is no permanent plastic change in volume within the accuracy of observation. A method is suggested whereby a correlation may be effected between the measured individual values of the Poisson's ratios and the stress-strain curves for the material. Allowance must be made for the difference in the stress-strain in tension and compression; this difference, wherever it appears, is accompanied by significant changes in the Poisson's ratios.
A polar-coordinate survey method for determining jet-engine combustion-chamber performance
No Description Available.
Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting
Program written to perform polynomial least squares fits on the the IBM 7090 computer.
Police regulation of aircraft
Different aspects of aircraft regulation are discussed such as: protecting the public; the restriction of flights over crowds; regulations of wing-walkers.
Polish P type single-seat fighters : all-metal gull-type wing monoplanes
No Description Available.
Polishing Methods for Metallic and Ceramic Transmission Electron Microscopy Specimens
"In recent years, the increasing sophistication of transmission electron microscope (TEM) studies of materials has necessitated more exacting methods of specimen preparation. The present report describes improved equipment and techniques for electropolishing and chemically polishing a wide variety of specimens. Many of the specimens used in developing or improving the techniques to be described were irradiated with heavy ions such as nickel or vanadium to study radiation damage. The high cost of these specimens increased the need for reproducible methods of initial preparation, postirradiaton processing, and final thinning for TEM examination. A technique was also developed to salvage specimens that had previously been thinned but were unusable for various reasons. Jet polishing is, in general, the method of choice for surface polishing, sectioning, and thinning. The older beaker electropolishing method is included in this report because it is inexpensive and simple, and gives some insight into how the more recent methods were developed. 29 figures, 8 tables. (ERA citation 07:004650)."--NTIS abstract.
Polishing Methods for Metallic and Ceramic Transmission Electron Microscopy Specimens, Rev. 1
"In recent years, the increasing sophistication of transmission electron microscope (TEM) studies of materials has necessitated more exacting methods of specimen preparation. The present report describes improved equipment and techniques for electropolishing and chemically polishing a wide variety of specimens. Many of the specimens used in developing or improving the techniques to be described were irradiated with heavy ions such as nickel or vanadium to study radiation damage. The high cost of these specimens increased the need for reproducible methods of initial preparation postirradiation processing, and final thinning for TEM examination. A technique was also developed to salvage specimens that had previously been thinned but were unusable for various reasons. Jet polishing is, in general, the method of choice for surface polishing, sectioning, and thinning. The older beaker electropolishing method is included in this report because it is inexpensive and simple, and gives some insight into how the more recent methods were developed"--NTIS abstract.