Latest content added for UNT Digital Libraryhttps://digital.library.unt.edu/search/?q5=&searchType=advanced&fq=dc_type%3Atext_report&t5=dc_subject&start=722019-08-27T15:53:11-05:00UNT LibrariesThis is a custom feed for searching UNT Digital LibraryFinal Report: Production Test No. 305-2-N Experimental Results Obtained From Test Pile Reactivity Measurements on Plutonium2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201857/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201857/"><img alt="Final Report: Production Test No. 305-2-N Experimental Results Obtained From Test Pile Reactivity Measurements on Plutonium" title="Final Report: Production Test No. 305-2-N Experimental Results Obtained From Test Pile Reactivity Measurements on Plutonium" src="https://digital.library.unt.edu/ark:/67531/metadc1201857/small/"/></a></p><p>Measurements were taken to provide experimental evidence for determining the feasibility of a proposed method for converting Pu240 to 241 by exposing shielded plutonium to selectively transmitted pile neutrons.</p>A Hanford Works Vacuum System2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201864/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201864/"><img alt="A Hanford Works Vacuum System" title="A Hanford Works Vacuum System" src="https://digital.library.unt.edu/ark:/67531/metadc1201864/small/"/></a></p><p>The remodeling, fabrication, and instrumentation of a high vacuum system are described. The faults encountered with the old system and their solution are outlined. Tests were made on diffusion pump oils and on the reduction of pump oil back diffusion. The measurement of high vacuum pressures by a cold cathode ionization gage at various points on a vacuum system are discussed.</p>Multiplication of Enriched Loading in Exponential Pile2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201896/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201896/"><img alt="Multiplication of Enriched Loading in Exponential Pile" title="Multiplication of Enriched Loading in Exponential Pile" src="https://digital.library.unt.edu/ark:/67531/metadc1201896/small/"/></a></p><p>This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.</p>Some Observations Regarding Rare-Earth Lactates2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201505/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201505/"><img alt="Some Observations Regarding Rare-Earth Lactates" title="Some Observations Regarding Rare-Earth Lactates" src="https://digital.library.unt.edu/ark:/67531/metadc1201505/small/"/></a></p><p>From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcohol to a sirupy solution. Since it was not as deliquescent as the lactates of lanthanum, cerium, and praseodymium, some of its properties could be studied. The lactates of all the other rare earths, samarium through lutetium, as well as the lactate of yttrium, separated readily from aqueous media as trihydrates--the solubility of the hydrated lactate decreasing as the atomic number of the rare earth increased. Thermal decomposition of the crystalline lactates, except those of neodymium and samarium, proceeded through dihydrated and anhydrous states to a composition corresponding roughly to LnlacCO3 at a temperature of about 290-300°C. Ln2(CO3)3 or Ln2O(Co3)2 were observed. In order to make a comparison, thermal decomposition of the rare-earth glycolates was studied also. Solubilities in water at both 20 and 60°C have been tabulated."</p>Electron Requirements of Bonds in Metal Borides2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201512/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201512/"><img alt="Electron Requirements of Bonds in Metal Borides" title="Electron Requirements of Bonds in Metal Borides" src="https://digital.library.unt.edu/ark:/67531/metadc1201512/small/"/></a></p><p>From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."</p>A Study of Plutonium Trifluoride Precipitated from Aqueous Solution2019-08-27T15:53:11-05:00https://digital.library.unt.edu/ark:/67531/metadc1201923/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201923/"><img alt="A Study of Plutonium Trifluoride Precipitated from Aqueous Solution" title="A Study of Plutonium Trifluoride Precipitated from Aqueous Solution" src="https://digital.library.unt.edu/ark:/67531/metadc1201923/small/"/></a></p><p>In view of the increasing number of methods for determining plutonium in terms of weight rather than radioactivity, a need has arisen for a plutonium compound that can be used as a gravimetric standard. An easily prepared compound that dissolves readily in nitric acid is desirable. The present study was made to determine the feasibility of using plutonium triflouride as a plutonium standard. The preparation, composition, stability, and ignition of the compound are discuss, as are certain properties of the plutonium dioxide resulting from ignition of the trifluoride.</p>Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 32019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1201965/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201965/"><img alt="Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3" title="Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3" src="https://digital.library.unt.edu/ark:/67531/metadc1201965/small/"/></a></p><p>Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.</p>Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.2019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1201973/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201973/"><img alt="Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures." title="Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures." src="https://digital.library.unt.edu/ark:/67531/metadc1201973/small/"/></a></p><p>Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.</p>BWR Reference Design for PL-32019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1202001/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1202001/"><img alt="BWR Reference Design for PL-3" title="BWR Reference Design for PL-3" src="https://digital.library.unt.edu/ark:/67531/metadc1202001/small/"/></a></p><p>Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and training program outline.</p>PWR Preliminary Design for PL-32019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1202002/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1202002/"><img alt="PWR Preliminary Design for PL-3" title="PWR Preliminary Design for PL-3" src="https://digital.library.unt.edu/ark:/67531/metadc1202002/small/"/></a></p><p>Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and a training program outline.</p>Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design2019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1201945/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201945/"><img alt="Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design" title="Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design" src="https://digital.library.unt.edu/ark:/67531/metadc1201945/small/"/></a></p><p>Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shut down, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The general arrangement of the heat exchanger described in this report presents a conventional design utilizing known materials and existing methods of fabrication. In further consideration of all concepts, designs and analyses developed during this period of the program, it is felt that this preliminary design will provide an intermediate sodium heat exchanger of lower cost and more reliable operation.</p>Aerial Radiometric and Magnetic Survey: McAllen/Brownsville National Topographic Map, Texas Gulf Coast, Volume 12019-07-23T13:35:56-05:00https://digital.library.unt.edu/ark:/67531/metadc958199/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc958199/"><img alt="Aerial Radiometric and Magnetic Survey: McAllen/Brownsville National Topographic Map, Texas Gulf Coast, Volume 1" title="Aerial Radiometric and Magnetic Survey: McAllen/Brownsville National Topographic Map, Texas Gulf Coast, Volume 1" src="https://digital.library.unt.edu/ark:/67531/metadc958199/small/"/></a></p><p>Final report documenting a high-sensitivity airborne gamma radiation and magnetic field survey of the Brownsville and McAllen National Topographic Map segments including a description of the program and results.</p>Aerial Radiometric and Magnetic Survey: Houston National Topographic Map, Texas Gulf Coast, Volume 12019-07-23T13:35:56-05:00https://digital.library.unt.edu/ark:/67531/metadc958196/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc958196/"><img alt="Aerial Radiometric and Magnetic Survey: Houston National Topographic Map, Texas Gulf Coast, Volume 1" title="Aerial Radiometric and Magnetic Survey: Houston National Topographic Map, Texas Gulf Coast, Volume 1" src="https://digital.library.unt.edu/ark:/67531/metadc958196/small/"/></a></p><p>Final report documenting a high-sensitivity airborne gamma radiation and magnetic field survey of the Houston National Topographic Map segment (NH 15-7 quadrangle) including a description of the program and results.</p>Aerial Radiometric and Magnetic Survey: Socorro National Topographic Map, New Mexico2019-04-27T17:45:58-05:00https://digital.library.unt.edu/ark:/67531/metadc958320/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc958320/"><img alt="Aerial Radiometric and Magnetic Survey: Socorro National Topographic Map, New Mexico" title="Aerial Radiometric and Magnetic Survey: Socorro National Topographic Map, New Mexico" src="https://digital.library.unt.edu/ark:/67531/metadc958320/small/"/></a></p><p>"The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Socorro National Topographic Map NI13-4 is presented in this report"--Abstract.</p>Explosion and Detonation Properties of Mixtures of Hydrogen, Oxygen, and Water Vapor2019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201251/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201251/"><img alt="Explosion and Detonation Properties of Mixtures of Hydrogen, Oxygen, and Water Vapor" title="Explosion and Detonation Properties of Mixtures of Hydrogen, Oxygen, and Water Vapor" src="https://digital.library.unt.edu/ark:/67531/metadc1201251/small/"/></a></p><p>From summary: "The hazards due to possible chemical explosion and detonation of the dissociation gases in homogeneous-reactor systems have been considered."</p>Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli2019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201128/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201128/"><img alt="Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli" title="Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli" src="https://digital.library.unt.edu/ark:/67531/metadc1201128/small/"/></a></p><p>From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."</p>Thermal Conductivity of Graphite2019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201146/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201146/"><img alt="Thermal Conductivity of Graphite" title="Thermal Conductivity of Graphite" src="https://digital.library.unt.edu/ark:/67531/metadc1201146/small/"/></a></p><p>Technical report outlining the differences in conductivity of AGOT graphite and AGHT graphite.</p>Disposition of Radiation Products and Energy Transfer in Radiobiological Processes2019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201063/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201063/"><img alt="Disposition of Radiation Products and Energy Transfer in Radiobiological Processes" title="Disposition of Radiation Products and Energy Transfer in Radiobiological Processes" src="https://digital.library.unt.edu/ark:/67531/metadc1201063/small/"/></a></p><p>Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.</p>The Effect of Aneuploidy Upon the Chromosome Number of Succeeding Generations of Tetraploid Maize2019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201064/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201064/"><img alt="The Effect of Aneuploidy Upon the Chromosome Number of Succeeding Generations of Tetraploid Maize" title="The Effect of Aneuploidy Upon the Chromosome Number of Succeeding Generations of Tetraploid Maize" src="https://digital.library.unt.edu/ark:/67531/metadc1201064/small/"/></a></p><p>Technical report outlining the effects of chromosomal abnormalities in tetraploid Argentine flint maize pollination, and subsequent generations.</p>Metallurgy Division Quarterly Progress Report for Period Ending January 31, 19522019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201236/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201236/"><img alt="Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952" title="Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952" src="https://digital.library.unt.edu/ark:/67531/metadc1201236/small/"/></a></p><p>This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.</p>Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 19512019-04-08T16:00:56-05:00https://digital.library.unt.edu/ark:/67531/metadc1201184/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201184/"><img alt="Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 1951" title="Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 1951" src="https://digital.library.unt.edu/ark:/67531/metadc1201184/small/"/></a></p><p>Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radiochemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses. [From Abstract]</p>Report of Stonewall Democrats of Texas Audit Committee2019-02-16T21:54:29-06:00https://digital.library.unt.edu/ark:/67531/metadc1452279/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1452279/"><img alt="Report of Stonewall Democrats of Texas Audit Committee" title="Report of Stonewall Democrats of Texas Audit Committee" src="https://digital.library.unt.edu/ark:/67531/metadc1452279/small/"/></a></p><p>Report of Stonewall Democrats of Texas Audit Committee covering financial policies and procedures, banking and compliance with Texas Ethics Commission's reporting requirements for General Political Action Committees.</p>Texas Stonewall Democratic Caucus Executive Board Meeting2019-02-16T21:54:29-06:00https://digital.library.unt.edu/ark:/67531/metadc1451685/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1451685/"><img alt="Texas Stonewall Democratic Caucus Executive Board Meeting" title="Texas Stonewall Democratic Caucus Executive Board Meeting" src="https://digital.library.unt.edu/ark:/67531/metadc1451685/small/"/></a></p><p>Minutes of members meeting of the Texas Stonewall Democratic Caucus on February 28, 2009. A breakdown of various topics discussed including other committee reports. Photocopy of Texas Stonewall Democratic Caucus custom summary report from January 1 through February 26, 2009. Photocopy of Texas Stonewall Democratic Caucus transaction detail by account of $858.44 from January 1 through February 26, 2009. Photocopy of Texas Stonewall Democratic Caucus custom summary report from July through December 2008. Photocopy of profit & loss budget vs. actual from February 2008 through January 2009 for the Texas Stonewall Democratic Caucus. Also, TSDC Board Meeting handwritten notes on February 28, 2009.</p>Calculations of fuel temperature transients in the LPTR following a main coolant system pump trip2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1449797/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1449797/"><img alt="Calculations of fuel temperature transients in the LPTR following a main coolant system pump trip" title="Calculations of fuel temperature transients in the LPTR following a main coolant system pump trip" src="https://digital.library.unt.edu/ark:/67531/metadc1449797/small/"/></a></p><p>An analysis was made to determine the fuel temperature in the Livermore Pool Type Reactor, LPTR, during a transient involving a reactor scram following a cooling system pump trip. A computer code was obtained for this purpose from the University of Virginia. This code was used in preparation of UVAR-18, the SAR Manual of the University of Virginia Reactor. This reactor is very similar to the LPTR. The code incorporates a form of the reactor point kinetics equation with six delayed neutron groups, and standard heat transfer equations. The code was modified for use in this study. These modifications included rewriting the code in Fortran IV from ALGO, replacing a straight line pump coastdown by an equation closely following the actual pump RPM during a pump trip, modifying flow resistance equations to conform to the conditions in the LPTR, and replacing various constants with others applicable to the LPTR. The calculations in this study apply to a reactor scram from conditions at the ''safety limit'' settings.</p>User's manual for the reactor burnup system, REBUS. [LMFBR]2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1450165/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1450165/"><img alt="User's manual for the reactor burnup system, REBUS. [LMFBR]" title="User's manual for the reactor burnup system, REBUS. [LMFBR]" src="https://digital.library.unt.edu/ark:/67531/metadc1450165/small/"/></a></p><p>A user's manual for the REBUS System (REactor BUrnup System) is presented. Its primary purpose is to provide sufficient information about the REBUS capability to the user to ensure its efficient utilization. The current REBUS System either solves for the infinite time (equilibrium) operating conditions of a recycle system under fixed conditions, or solves for operating conditions during a single time step (non-equilibrium). The capability of studying various in-reactor fuel management and ex-reactor fuel management schemes has been included. REBUS has been operated with one- and two-dimensional diffusion theory neutronics solutions up to the present time. The model was specifically designed for extension to other neutronics models such as three-dimensional diffusion or transport theory and direct or synthesis solutions.</p>Studies of encapsulation materials for terrestrial photovoltaic arrays. Third quarterly progress report, March 16, 1976--June 15, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1450076/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1450076/"><img alt="Studies of encapsulation materials for terrestrial photovoltaic arrays. Third quarterly progress report, March 16, 1976--June 15, 1976" title="Studies of encapsulation materials for terrestrial photovoltaic arrays. Third quarterly progress report, March 16, 1976--June 15, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1450076/small/"/></a></p><p>Most of this report is concerned with Study 4, ''Development of Accelerated and Abbreviated Testing Methods for Predicting Performance of Encapsulation Materials Over a 20-Year Lifetime.'' The outputs of the study are to be (1) the specification of a methodology for developing the experimental designs for aging tests, and (2) the development of the experimental designs for aging tests for selected materials and material interfaces. Pursuant to these goals, the aging behavior of polymeric materials has been reviewed to lead to identifying possible failure mechanisms and thus to appropriate choices of characteristics to be measured and stresses to be used in accelerated/abbreviated tests. A similar review has been made for glasses. The results are discussed. Aging data and data analysis methods (models) which have been used in other investigations have been identified and critiqued; these results are presented. Initial results of efforts on developing the methodology are also presented in the discussion. (WDM)</p>Physiopathology of blood platelets and development of platelet substitutes. Progress report, August 1, 1975--July 31, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1443363/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1443363/"><img alt="Physiopathology of blood platelets and development of platelet substitutes. Progress report, August 1, 1975--July 31, 1976" title="Physiopathology of blood platelets and development of platelet substitutes. Progress report, August 1, 1975--July 31, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1443363/small/"/></a></p><p>Progress is reported on studies on the physiology of blood platelets in thrombocytopenic patients and rabbits. Methods for the detection of platelet antibodies and the preservation of platelets in vitro were investigated. Studies on the effect of low doses of x irradiation (up to 1000 R) on platelet function indicate that platelets exposed to ionizing radiation have increased functional activity. A list is included of publications that report the results of the studies in detail.</p>Nuclear chemistry and geochemistry research. Carnegie Institute of Technology and Carnegie--Mellon University. Summary report2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1443529/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1443529/"><img alt="Nuclear chemistry and geochemistry research. Carnegie Institute of Technology and Carnegie--Mellon University. Summary report" title="Nuclear chemistry and geochemistry research. Carnegie Institute of Technology and Carnegie--Mellon University. Summary report" src="https://digital.library.unt.edu/ark:/67531/metadc1443529/small/"/></a></p><p>A summary is presented of the activities and results of research in nuclear chemistry, nuclear geochemistry, nuclear cosmochemistry, and other minor areas from 1950 to 1976. A complete listing is given of publications, doctoral dissertations, and reports resulting from the research. A chronological list provides an overview of the activities at any particular time. (JSR)</p>Analysis of nuclear stimulation of Reservoir A, U. S. S. R2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1442736/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1442736/"><img alt="Analysis of nuclear stimulation of Reservoir A, U. S. S. R" title="Analysis of nuclear stimulation of Reservoir A, U. S. S. R" src="https://digital.library.unt.edu/ark:/67531/metadc1442736/small/"/></a></p><p>Following stimulation by three nuclear explosives, the field rate of production of ''Reservoir A'', U.S.S.R., increased very significantly. The potential profitability of projects such as Reservoir A and some of the possible causes for the increased rate of production are reviewed.</p>Instruction manual for Gunn-diode microwave cavity ammonia monitor2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1443429/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1443429/"><img alt="Instruction manual for Gunn-diode microwave cavity ammonia monitor" title="Instruction manual for Gunn-diode microwave cavity ammonia monitor" src="https://digital.library.unt.edu/ark:/67531/metadc1443429/small/"/></a></p><p>The Gunn-diode microwave cavity instrument is a self-contained (the vacuum pump is external) microwave spectrometer for the specific detection and monitoring of ammonia gas in air. A solid state microwave source is used together with a high-Q resonant microwave cavity which is both the frequency selecting device for the source and the sample container through which the sampled gases pass. The ammonia absorption transition at 23,870.1 MHz is monitored continuously with this instrument. The monitoring frequency is stable to one part in 10/sup 9/ so that the system only responds to NH/sub 3/ absorption--there are no known interfering gases. The instrument was designed for simple operation and easy calibration. Except for the calibration procedure, the instrument operates automatically from turn-on. A four-digit readout is supplied on the front panel and it reads the concentration of ammonia directly in parts-per-million over a range of from 0.00 to 20 ppM. A 0 to 10 volt output is also available at the rear panel for recording data on an external recorder.</p>Web-dendritic ribbon growth. Quarterly report, October 1976--December 15, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1447858/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1447858/"><img alt="Web-dendritic ribbon growth. Quarterly report, October 1976--December 15, 1976" title="Web-dendritic ribbon growth. Quarterly report, October 1976--December 15, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1447858/small/"/></a></p><p>A report of the fifth quarter's work on the web-dendritic ribbon growth at the University of South Carolina is presented. A brief description of the work initiated and carried out during this period to meet the program goals is given along with a copy of the Program Plan covering the entire period of the contract. The web growth portion of this program was spent in the design, installation and testing of a new furnace geometry for the growth of dendritic web ribbon. The new installation was completed and the testing 90% accomplished. Results of the testing to determine the effect of the relative position of the r.f. coil with respect to the susceptor on the thermal profile in the melt are described. The one-dimensional thermal model has been used to determine the relationship between growth rate, web thickness, and mensicus height for stable growth. The results of this analysis are also given. An analysis was completed of the thermal radiation from the meniscus including the effect of the curvature of the meniscus with the results indicating that inclusion of the curvature leads to approximately a 10% increase in the radiation loss.</p>Synthetic-pitch binders by autoclave polymerization of organics2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1448446/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1448446/"><img alt="Synthetic-pitch binders by autoclave polymerization of organics" title="Synthetic-pitch binders by autoclave polymerization of organics" src="https://digital.library.unt.edu/ark:/67531/metadc1448446/small/"/></a></p><p>Polymers prepared by autoclave heat treatment of simple hydrocarbons were evaluated as sources of synthetic pitches for use in fabricating composite carbons. Hydrocarbons included: indene, phenanthrene, triphenylbenzene, 1,4-diphenyl-1,3-butadiyne, and cinnamylideneindene. Autoclave temperatures and pressures were in the ranges of 340 to 515/sup 0/C and 5 to 28 MPa, respectively. The more promising pitch materials were liquids or low-melting solids with coke yields of approximately 50 weight percent. Binary mixtures of organics were able to produce polymers and resulting carbons with properties that were correlated to the composition of the organic blend, thus allowing the controlled modification of properties.</p>Apparatus for spot welding sheathed thermocouples to the inside of small-diameter tubes at precise locations2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1448302/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1448302/"><img alt="Apparatus for spot welding sheathed thermocouples to the inside of small-diameter tubes at precise locations" title="Apparatus for spot welding sheathed thermocouples to the inside of small-diameter tubes at precise locations" src="https://digital.library.unt.edu/ark:/67531/metadc1448302/small/"/></a></p><p>Equipment and procedures used to spot weld tantalum- or stainless-steel-sheathed thermocouples to the inside diameter of Zircaloy tubing to meet the requirements of the Multirod Burst Test (MRBT) Program at ORNL are described. Spot welding and oxide cleaning tools were fabricated to remove the oxide coating on the Zircaloy tubing at local areas and spot weld four thermocouples separated circumferentially by 90/sup 0/ at any axial distribution desired. It was found necessary to apply a nickel coating to stainless-steel-sheathed thermocouples to obtain acceptable welds. The material and shape of the inner electrode and resistance between inner and outer electrodes were found to be critical parameters in obtaining acceptable welds.</p>Mark I 1/5-scale boiling water reactor pressure suppression experiment summary of effects due to vent line orifice variations: air test series2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1444275/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1444275/"><img alt="Mark I 1/5-scale boiling water reactor pressure suppression experiment summary of effects due to vent line orifice variations: air test series" title="Mark I 1/5-scale boiling water reactor pressure suppression experiment summary of effects due to vent line orifice variations: air test series" src="https://digital.library.unt.edu/ark:/67531/metadc1444275/small/"/></a></p><p>Twenty-seven air tests have been completed in the /sup 1///sub 5/-scale Mark I test facility. The observed effects of vent line orifice variations on the hydrodynamic vertical load function (HVLF) are presented. The conditions for standard tests, to which the orifice variation tests are compared, are defined and discussed. These tests used the ''standard'' or 9.5 inch orifices in the 90/sup 0/ sector vent lines.</p>Natural hazards that may trigger a radiological release from a plutonium processing facility2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1444649/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1444649/"><img alt="Natural hazards that may trigger a radiological release from a plutonium processing facility" title="Natural hazards that may trigger a radiological release from a plutonium processing facility" src="https://digital.library.unt.edu/ark:/67531/metadc1444649/small/"/></a></p><p>Calculations show the probability of a tornado striking a plutonium area at Rocky Flats is 2.2 x 10/sup -4/ per year. The source term (expected value of plutonium release) should such an event occur is calculated at 3.3 x 10/sup -7/ grams. The source term for high-velocity, downslope winds is higher--2.2 x 10/sup -3/ grams. The probability of a meteorite that weighs one or more pounds (453 grams) striking a plutonium area is estimated at 8.88 x 10/sup -7/ per year. Because of this small probability and the remote chance that a plutonium release would occur even if a meteorite hit occurred, the hazard from meteorite impact is considered negligible. Conservative assumptions result in all calculated frequencies being almost certainly too high. Empirical observations have indicated lower frequencies than those calculated.</p>Studies of encapsulation materials for terrestrial photovoltic arrays. Forth quarterly progress report, June 16, 1976--September 15, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1444652/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1444652/"><img alt="Studies of encapsulation materials for terrestrial photovoltic arrays. Forth quarterly progress report, June 16, 1976--September 15, 1976" title="Studies of encapsulation materials for terrestrial photovoltic arrays. Forth quarterly progress report, June 16, 1976--September 15, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1444652/small/"/></a></p><p>A report is presented on four studies on encapsulation: (1) Evaluation of world experience and properties of materials for encapsulation of terrestrial photovoltaic arrays; (2) Definition of encapsulant service environments and test conditions; (3) Evaluation of properties of encapsulation materials; and (4) Development of accelerated and abbreviated testing mathods for predicting performance of encapsulation materials over a 20-year lifetime. (WDM)</p>Harmonics suppression in electromagnets with application to the ALS storage ring corrector magnet design2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1444483/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1444483/"><img alt="Harmonics suppression in electromagnets with application to the ALS storage ring corrector magnet design" title="Harmonics suppression in electromagnets with application to the ALS storage ring corrector magnet design" src="https://digital.library.unt.edu/ark:/67531/metadc1444483/small/"/></a></p><p>This memo presents an analytical development for prediction of skew harmonics in a iron core C-magnet to due arbitrarily positioned electromagnet coils. A structured approach is presented for the suppression of an arbitrary number of harmonic components to arbitrarily low values. Application of the analytical harmonic strength calculations coupled to the structured harmonic suppression approach is presented in the context of the design of the ALS storage ring corrector magnets.</p>Neutral currents and parity breakdown in atomic transitions: three proposed experiments2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1449199/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1449199/"><img alt="Neutral currents and parity breakdown in atomic transitions: three proposed experiments" title="Neutral currents and parity breakdown in atomic transitions: three proposed experiments" src="https://digital.library.unt.edu/ark:/67531/metadc1449199/small/"/></a></p><p>This paper describes three proposed experiments for observing the breakdown of parity in atomic transitions due to the exchange of neutral, parity-violating currents arising from some of the new gauge models (e.g., the Weinberg model) for the weak interaction. The experiments are based on exploiting a suggestion, by Bouchiat and Bouchiat, that modern laser technology be utilized to produce intense, monochromatic, and polarized photon beams with which to excite forbidden atomic transitions of the basic form parallel ns/sup 1///sub 2/ broken bracket ..-->.. parallel n's/sup 1///sub 2/ broken bracket. The asymmetries (of the order of 10/sup -4/) in the de-exitation processes then signal the presence of the parity-violating components due to the neutral currents. In all three experiments suggested here, the use of multiple (uncollimated)atomic beams as targets forms a basic part, and their advantages over a temperature-equilibrium vapor are described. The first experiment uses /sup 55/Cs atomic beams as a target; the second uses /sup 37/Rb in conjunction with a superstrong magnetic field (approximately 80 kG); the third uses /sup 81/Tl and requires frequency doubling of the exciting laser beam. All three experiments appear to be quite feasible, and, given the requisite equipment (much of which is or soon will be commercially available), they could yield definitive results in a period of a few months.</p>Aerial radiometric and magnetic survey: Socorro National Topographic Map, New Mexico2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1449205/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1449205/"><img alt="Aerial radiometric and magnetic survey: Socorro National Topographic Map, New Mexico" title="Aerial radiometric and magnetic survey: Socorro National Topographic Map, New Mexico" src="https://digital.library.unt.edu/ark:/67531/metadc1449205/small/"/></a></p><p>The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Socorro National Topographic Map NI13-4 is presented in this report. The airborne data gathered are reduced by ground computer facilities to yield profile plots of the basic uranium, thorium and potassium equivalent gamma radiation intensities, ratios of these intensities, aircraft altitude above the earth's surface, total gamma ray and earth's magnetic field intensity, correlated as a function of geologic units. The distribution of data within each geologic unit, for all surveyed map lines and tie lines, has been calculated and is included. Two sets of profiled data for each line are included, with one set displaying the above-cited data. The second set includes only flight line magnetic field, temperature, pressure, altitude data plus magnetic field data as measured at a base station. A general description of the area, including descriptions of the various geologic units and the corresponding airborne data, is included.</p>Pacific Northwest Laboratory FY 1993 Site Maintenance Plan for maintenance of DOE nonnuclear facilities2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1448843/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1448843/"><img alt="Pacific Northwest Laboratory FY 1993 Site Maintenance Plan for maintenance of DOE nonnuclear facilities" title="Pacific Northwest Laboratory FY 1993 Site Maintenance Plan for maintenance of DOE nonnuclear facilities" src="https://digital.library.unt.edu/ark:/67531/metadc1448843/small/"/></a></p><p>This Site Maintenance Plan has been developed for Pacific Northwest Laboratory's (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance Procedures and Other Work-Related Documents; Scheduling System; Post Maintenance Testing; Backlog Work Control; Equipment Repair History and Vendor Information; Work Sampling; and Identification and Control. Based upon a graded approach and current funding, those elements considered most important have been selected as goals for earliest compliance. Commitment dates for these elements have been established for compliance. The remaining elements of noncompliance will be targeted for implementation during later budget periods.</p>Demonstration of an inductor motor/alternator/flywheel energy storage system. Technical quarterly progress report No. 2, September 28, 1976--December 28, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1448523/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1448523/"><img alt="Demonstration of an inductor motor/alternator/flywheel energy storage system. Technical quarterly progress report No. 2, September 28, 1976--December 28, 1976" title="Demonstration of an inductor motor/alternator/flywheel energy storage system. Technical quarterly progress report No. 2, September 28, 1976--December 28, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1448523/small/"/></a></p><p>The overall objective of the ERDA program described is to demonstrate new technology associated with a novel concept for a high-speed flywheel energy storage system. The concept, consisting of a high-speed composite flywheel combined with an integral inductor-type motor/alternator, offers the possibility of a small, lightweight package with high energy storage capability. The basic technology demonstrated in this program will have application to a number of flywheel energy storage systems. The demonstration unit will have a nominal rating of 20 kVA. The program will develop a flywheel energy storage system sized for a 3000 lb battery electric van. The balance of the report discusses the energy storage package: (1) design and fabrication of the inductor motor/alternator/flywheel; and (2) design and fabrication of the solid state power conditioner and control breadboard.</p>Dip coating process. Silicon sheet growth development for the large-area silicon sheet task of the low-cost silicon solar array project. Quarterly report No. 4, September 17, 1976--December 17, 19762019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445405/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445405/"><img alt="Dip coating process. Silicon sheet growth development for the large-area silicon sheet task of the low-cost silicon solar array project. Quarterly report No. 4, September 17, 1976--December 17, 1976" title="Dip coating process. Silicon sheet growth development for the large-area silicon sheet task of the low-cost silicon solar array project. Quarterly report No. 4, September 17, 1976--December 17, 1976" src="https://digital.library.unt.edu/ark:/67531/metadc1445405/small/"/></a></p><p>The objective of this research program is to investigate the technical and economic feasibility of producing solar cell-quality sheet silicon by coating one surface of carbonized ceramic substrates with a thin layer of large-grain polycrystalline silicon from the melt. With the present dip coating facility, pulling rates of 5 to 7 cm/min are most likely to produce layers of the crystalline quality from which high efficiency solar cells can be fabricated. At a pulling rate of 6 cm/min, it is possible to achieve smooth 50-..mu..m thick layers, with grains as large as 2.5-mm wide, generally extending the entire length of the substrate. At pulling rates less than 6 cm/min, single grains as large as 4 mm in width have been observed. Substrates held at an angle of 45/sup 0/ to the surface of the melt during dipping produced layers qualitatively similar to the vertical dipped layers, but they show some potential for improved coating uniformity. Diffractometer measurements on several samples showed that the strongest diffraction peak was from the silicon 220 plane which is about 10/sup 0/ from the sample surface. The (110) surfaces have been found to be dominant in the EFG and dendritic material, and it appears this is a general characteristic of sheet-grown silicon. Mullite substrates containing an excess of SiO/sub 2/ have been shown to match the thermal expansion coefficient of silicon. Mullite, however,dissolves slightly in the silicon melt, adding aluminum impurities to the silicon layers. A preliminary Ion Beam Microprobe analysis revealed that the aluminum concentration measured in three samples of typical dip-coated silicon layers correlated correctly with the measured restitivies. Photodiodes were made on a number of silicon on ceramic (SOC) layers, and results of performance tests are discussed.</p>1964 computer run on a laser-imploded capsule2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445372/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445372/"><img alt="1964 computer run on a laser-imploded capsule" title="1964 computer run on a laser-imploded capsule" src="https://digital.library.unt.edu/ark:/67531/metadc1445372/small/"/></a></p><p>WAZER Alchemy 7b (WA-7b) is a WAZER calculation of a laser-driven micro-implosion of a spherical capsule consisting of a thin gold pusher surrounded by a thick (frozen) deuterium ablator. The properties of the target capsule and the shape of the laser pulse used to irradiate it are described.</p>LAPACK Working Note 9: A test matrix generation suite2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445267/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445267/"><img alt="LAPACK Working Note 9: A test matrix generation suite" title="LAPACK Working Note 9: A test matrix generation suite" src="https://digital.library.unt.edu/ark:/67531/metadc1445267/small/"/></a></p><p>We discuss the design and implementation of a suite of test matrix generators for testing linear algebra software. These routines generate random matrices with certain properties which are useful for testing linear equation solving, least squares, and eigendecomposition software. These properites include the spectrum, symmetry, bandwidth, norm, sparsity, conditioning (with respect to inversion or for the eigenproblem), type (real or complex), and storage scheme (dense, packed or banded).</p>Clinch River Environmental Restoration Program2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445270/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445270/"><img alt="Clinch River Environmental Restoration Program" title="Clinch River Environmental Restoration Program" src="https://digital.library.unt.edu/ark:/67531/metadc1445270/small/"/></a></p><p>This report consists of tables and listings from the results of the Phase I data gathering activities of the Clinch River Environmental Restoration Program (CR-ERP). The table of contents outlines the presentation of the material and has been annotated to indicate the key fields used to order the printing of each data table. Definitions of selected column headings are provided. Sample collection information is shown first and then more specific information for each matrix type is presented. The analytical results have been reviewed by independent validators and the qualifiers shown are the results of their efforts. No data that were rejected by the validation process are included in this listing. Only results of routine samples are listed; quality control sample results were excluded. All data, both detected and nondetected values, were used to calculated the summary table values. However, only Detected values are given on the analyte specific listings.</p>Use of geochemical-equilibrium computer calculations to estimate precipitation from geothermal brines2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445768/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445768/"><img alt="Use of geochemical-equilibrium computer calculations to estimate precipitation from geothermal brines" title="Use of geochemical-equilibrium computer calculations to estimate precipitation from geothermal brines" src="https://digital.library.unt.edu/ark:/67531/metadc1445768/small/"/></a></p><p>The Helgeson-Herrick geochemical code was used to calculate the solubility of NaCl, KCl, and KCl-NaCl in water and to predict which minerals will precipitate from Salton Sea Geothermal Field brines. The code's predictions of sulfide-silicate precipitation from the Magmamax No. 1 brine are in good agreement with field tests of scaling, although the observed sulfide-silicate scale matrix is in amorphous form, rather than the crystalline form predicted by the code. The code's predictions of scale precipitation from wells with different brine compositions are also in good agreement with field tests. The code appears to be a useful screening tool, despite reservations about the use of purely thermodynamic predictions in systems with important kinetic constraints. Several ways to improve and apply the code in the future are suggested.</p>Comment on Flavor-Changing Processes and CP Violation in the S Sub 3 Times Z Sub 3 Model''2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1446189/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1446189/"><img alt="Comment on Flavor-Changing Processes and CP Violation in the S Sub 3 Times Z Sub 3 Model''" title="Comment on Flavor-Changing Processes and CP Violation in the S Sub 3 Times Z Sub 3 Model''" src="https://digital.library.unt.edu/ark:/67531/metadc1446189/small/"/></a></p><p>Deshpande, Gupta and Pal neglected the presence of a complex phase in the mass matrix and in the Yukawa coupling matrices of the down-type quarks I argue that phase should not be neglected, because it can explain the observed CP violation. The mechanism of CP violation considered by those authors may certainly be present, but for simplicity one may want to eliminate it, by restricting the soft-breaking sector of the Higgs potential in such a way that complex Higgs bosons propagators do not occur.</p>Characterizing cinder rock with the scanning electron microscope. [From in-situ retorting]2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1445570/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1445570/"><img alt="Characterizing cinder rock with the scanning electron microscope. [From in-situ retorting]" title="Characterizing cinder rock with the scanning electron microscope. [From in-situ retorting]" src="https://digital.library.unt.edu/ark:/67531/metadc1445570/small/"/></a></p><p>Friable cinder rock was examined by scanning electron microscopy and energy dispersive x-ray analysis (SEM/ED). The technique consisted of impregnating the rock with epoxy resin and then locating porosity sites by the presence of epoxy. The resin was identified in the sample by correlating beam damage and elemental analysis by x-ray fluorescence (ED) with a characteristic phase in the SEM image. Analyses of this type should be useful in interpreting experiments designed to simulate in situ retorting.</p>Neutron and fission yields from high-energy deuterons in infinite /sup 238/U targets2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1447419/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1447419/"><img alt="Neutron and fission yields from high-energy deuterons in infinite /sup 238/U targets" title="Neutron and fission yields from high-energy deuterons in infinite /sup 238/U targets" src="https://digital.library.unt.edu/ark:/67531/metadc1447419/small/"/></a></p><p>Early work on the interaction of high energy deuterons with large /sup 238/U targets is reexamined and current theoretical study is discussed. Results of fission and neutron yield calculations are compared with experiment. (SDF)</p>The kinetics of sulfation of calcium oxide2019-02-10T20:45:37-06:00https://digital.library.unt.edu/ark:/67531/metadc1447382/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1447382/"><img alt="The kinetics of sulfation of calcium oxide" title="The kinetics of sulfation of calcium oxide" src="https://digital.library.unt.edu/ark:/67531/metadc1447382/small/"/></a></p><p>The objectives of this study are to determine the intrinsic kinetics and the product layer diffusion rate by minimizing the resistances to gas-phase pore diffusion, and eliminating complications due to pore filling. In the report, a grain model was used to introduce the various potentially rate-limiting processes. It was compared with results obtained with a distributed pore model by Bhatia Perlmutter (1981). Comparing the predicted behavior of the surface areas with conversion, it was even possible to compare experimental results with other models. The conclusion of this study was that, even thought the kinetic parameters obtained with different samples differed much more if product layer diffusion assumed rate-limiting rather than the surface reaction, the shape of the predicted curve approached the experimental findings so much better, that product layer diffusion is indeed most likely to be rate-limiting. (VC)</p>