Latest content added for UNT Digital Library Searchhttps://digital2.library.unt.edu/search/?t=fulltext&fq=str_day%3A25&sort=default2018-02-04T10:51:49-06:00UNT LibrariesThis is a custom feed for searching UNT Digital Library SearchComments on septa and other small production angle magnets2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1055770/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1055770/"><img alt="Comments on septa and other small production angle magnets" title="Comments on septa and other small production angle magnets" src="https://digital.library.unt.edu/ark:/67531/metadc1055770/thumbnail/"/></a></p><p>A discussion is given of possible septum magnet parameters for small production angle experiments in the ISABELLE storage rings. Superconducting septa and torroidal septa are also considered. (PMA)</p>PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1055354/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1055354/"><img alt="PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING" title="PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING" src="https://digital.library.unt.edu/ark:/67531/metadc1055354/thumbnail/"/></a></p><p>The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)</p>Configuration Management Program Plan2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1055345/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1055345/"><img alt="Configuration Management Program Plan" title="Configuration Management Program Plan" src="https://digital.library.unt.edu/ark:/67531/metadc1055345/thumbnail/"/></a></p><p>Westinghouse Savannah River Company (WSRC) has established a configuration management (CM) plan to execute the SRS CM Policy and the requirements of the DOE Order 4700.1. The Reactor Restart Division (RRD) has developed its CM Plan under the SRS CM Program and is implementing it via the RRD CM Program Plan and the Integrated Action Plan. The purpose of the RRD CM program is to improve those processes which are essential to the safe and efficient operation of SRS production reactors. This document provides details of this plan.</p>Preliminary design data package. Appendices C1 and C3. [HYBRID 2; VSYS; and CRASH]2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1055282/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1055282/"><img alt="Preliminary design data package. Appendices C1 and C3. [HYBRID 2; VSYS; and CRASH]" title="Preliminary design data package. Appendices C1 and C3. [HYBRID 2; VSYS; and CRASH]" src="https://digital.library.unt.edu/ark:/67531/metadc1055282/thumbnail/"/></a></p><p>The computer programs, including HYBRID, VSYS, VEHIC and CRASH, used to compute the energy and fuel consumption, life-cycle costs and performance characteristics of a hybrid electric-powered vehicle are described and their use documented. (LCL)</p>Theoretical study of the structure, energetics, and dynamics of silicon and carbon systems using tight-binding approaches2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1056203/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1056203/"><img alt="Theoretical study of the structure, energetics, and dynamics of silicon and carbon systems using tight-binding approaches" title="Theoretical study of the structure, energetics, and dynamics of silicon and carbon systems using tight-binding approaches" src="https://digital.library.unt.edu/ark:/67531/metadc1056203/thumbnail/"/></a></p><p>Semiempirical interatomic potentials are developed for silicon and carbon by modeling the total energy of the system using tight-binding approaches. The parameters of the models were obtained by fitting to results from accurate first-principles Local Density Functional calculations. Applications to the computation of phonons as a function of volume for diamond-structured silicon and carbon and the thermal expansions for silicon and diamond yields results which agree well with experiment. The physical origin of the negative thermal expansion observed in silicon is explained. A tight-binding total energy model is generated capable of describing carbon systems with a variety of atomic coordinations and topologies. The model reproduces the total energy versus volume curves of various carbon polytypes as well as phonons and elastic constants of diamond and graphite. The model has also been used in the molecular-dynamics simulation of the properties of carbon clusters. The calculated ground-state geometries of small clusters (C{sub 2}--C{sub 10}) correlates well with results from accurate quantum chemical calculations, and the structural trend of clusters from C{sub 2} to C{sub 60} are investigated. 67 refs., 19 figs.</p>EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058448/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058448/"><img alt="EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP" title="EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP" src="https://digital.library.unt.edu/ark:/67531/metadc1058448/thumbnail/"/></a></p><p>Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)</p>A cryogenic system design for the international thermonuclear experimental reactor (ITER)2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058544/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058544/"><img alt="A cryogenic system design for the international thermonuclear experimental reactor (ITER)" title="A cryogenic system design for the international thermonuclear experimental reactor (ITER)" src="https://digital.library.unt.edu/ark:/67531/metadc1058544/thumbnail/"/></a></p><p>A conceptual design for ITER was completed last year. The author developed a suitable cryogenic system for ITER as part of this conceptual design effort. An overview of the design is reported. Emphasis is on the fact that cryogenics is a mature science, and a system supporting ITER needs can be made from time-proven components without loss of efficiency or reliability. Because of the large size of the ITER cryogenic system, large numbers of compressors and expanders must be used. Very high reliability is assured by arranging these components in parallel banks where servicing of individual components can be done without interruption of operations. This and other ideas based on the author's experience with Mirror Fusion Test Facility (MFTF) operations are described. 5 refs., 3 figs.</p>GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058895/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058895/"><img alt="GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES" title="GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES" src="https://digital.library.unt.edu/ark:/67531/metadc1058895/thumbnail/"/></a></p><p>S>The compatibility of type 304L stainless steel in intimate contact with graphite is being studied as a function of temperature and contact pressure. This study is an outgrowth of materials compatibility problems in present and advanced gas-cooled reactors, where structural members in direct contact with graphite provide the possibility of both carburization and self-welding. Initial studies were concerned with surface reactions in the absence of gaseous contaminants under a vacuum of 10/sup -6/ mm Hg at 540 to 705 deg C. Stainless steel specimens are pretreated to provide three surface conditions: H/sub 2/- fired, preoxidized, and Cu-plated. Surface contact pressures ranged from 0 to 10,000 psi. Test results are presented which establish the lower temperature limit for significant diffusion between graphite and stainless steel at approximately 60O deg C. Above this temperature, diffusion between untreated or H2-fired stainless steel surfaces was found to effect complete bonding of the two materials at contact pressures as low as 500 psi. Bonding was effectively prevented by the presence of either an oxide film or a Cu plate at temperatures up to 700 deg C. Where bonding occurred, diffusion rates measured for C in stainless steel were comparable with those reported for stainless steel ln C- saturated Na. However, phases produced in surface reactions between graphite and stainless steel were of higher order than those reported for the Na carrier. Lack of carburization in control specimens not in contact with graphite indicated the role of the gas phase to be unimportant at impurity pressures of 10/sup -6/ mm Hg. (auth)</p>Pakistan: A Bibliography2017-11-05T17:47:57-06:00https://digital.library.unt.edu/ark:/67531/metadc1038995/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1038995/"><img alt="Pakistan: A Bibliography" title="Pakistan: A Bibliography" src="https://digital.library.unt.edu/ark:/67531/metadc1038995/thumbnail/"/></a></p><p>This report is a bibliography that cites information related to Pakistan. It includes General, History, Government and Politics, Economy and Development, Foreign policy, and defense.</p>The Military Selective Service Act of 1967:Its Basic Provisions and Implementation by Executive Order 113602017-11-05T17:47:57-06:00https://digital.library.unt.edu/ark:/67531/metadc1039043/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1039043/"><img alt="The Military Selective Service Act of 1967:Its Basic Provisions and Implementation by Executive Order 11360" title="The Military Selective Service Act of 1967:Its Basic Provisions and Implementation by Executive Order 11360" src="https://digital.library.unt.edu/ark:/67531/metadc1039043/thumbnail/"/></a></p><p>This report describes an outline of provisions for Military selective service act of 1967 and changes to it that effected through the executive order 11360.</p>Do-It-Yourself Ecology2017-11-05T17:47:57-06:00https://digital.library.unt.edu/ark:/67531/metadc1039001/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1039001/"><img alt="Do-It-Yourself Ecology" title="Do-It-Yourself Ecology" src="https://digital.library.unt.edu/ark:/67531/metadc1039001/thumbnail/"/></a></p><p>This report deals with how to develop a good environment.</p>Major Natural Disasters in the United States: 1959-19692017-11-05T17:47:57-06:00https://digital.library.unt.edu/ark:/67531/metadc1039078/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1039078/"><img alt="Major Natural Disasters in the United States: 1959-1969" title="Major Natural Disasters in the United States: 1959-1969" src="https://digital.library.unt.edu/ark:/67531/metadc1039078/thumbnail/"/></a></p><p>This report provides a listing of major natural disasters in the United States between 1959 and 1969. It lists the name of the event, the estimated costs of damage, and fatality numbers for each disaster.</p>Kilowatt Isotope Power System: component test report for the Ground Demonstration System Alternator Stator2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1056948/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1056948/"><img alt="Kilowatt Isotope Power System: component test report for the Ground Demonstration System Alternator Stator" title="Kilowatt Isotope Power System: component test report for the Ground Demonstration System Alternator Stator" src="https://digital.library.unt.edu/ark:/67531/metadc1056948/thumbnail/"/></a></p><p>Results are presented of acceptance tests conducted on the Alternator Stator, S/N 002, for the Kilowatt Isotope Power System. These results show that the Alternator Stator, S/N 002 for the Kilowatt Isotope Power System has satisfactorily completed the testing set forth within Sundstrand Test Specification 2538. Test requirements of TS 2538 were extracted from the Kilowatt Isotope Power System, and Phase I Test Plan.</p>Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 19802018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1057563/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1057563/"><img alt="Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980" title="Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980" src="https://digital.library.unt.edu/ark:/67531/metadc1057563/thumbnail/"/></a></p><p>Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.</p>Monthly energy review, October 1991. [Contains glossary]2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1057379/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1057379/"><img alt="Monthly energy review, October 1991. [Contains glossary]" title="Monthly energy review, October 1991. [Contains glossary]" src="https://digital.library.unt.edu/ark:/67531/metadc1057379/thumbnail/"/></a></p><p>This report presents current data on production, consumption, stocks, imports, exports, and prices of the principal energy commodities in the United States. Also included are data on international production of crude oil, consumption of petroleum products, petroleum stocks, and production of electricity from nuclear-powered facilities. 36 figs., 57 tabs.</p>Assessment of the potential of colloidal fuels in future energy usage. Final report. [97 references]2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1057226/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1057226/"><img alt="Assessment of the potential of colloidal fuels in future energy usage. Final report. [97 references]" title="Assessment of the potential of colloidal fuels in future energy usage. Final report. [97 references]" src="https://digital.library.unt.edu/ark:/67531/metadc1057226/thumbnail/"/></a></p><p>Pulverized coal has been an increasing important source of energy over the past century. Most large utility boilers, all modern coking plants, and many industrial boilers and blast furnaces employ pulverized coal as a major feed stream. In periods of oil shortages, such as during World Wars I and II, the concept of adding powdered coal to oil for use in combustion equipment originally designed for oil has been actively pursued but rarely used. Over this same period of time, there have been attempts to use air suspensions of coal dust in diesel engines in Germany, and in turbines in various countries. The economic advantages to be enjoyed by substitution of powdered coal in oil are not generally realized. Oil costs at $30/bbl represent a fuel value of about $5.00/10/sup 6/ Btu; coal at $25/ton is equivalent to approximately $1.00/10/sup 6/ Btu. Although capital costs for the use of coal are higher than those associated with the use of oil, coal is clearly becoming the least costly fuel. Not only are considerable cost advantages possible, but an improvement in balance of payments and an increase in reliability of fuel supplies are other potential benefits. It is therefore recommended that increased national attention be given to develop these finer grinds of carbonaceous fuels to be used in various suspending fluids. Technical areas where significant additional support appear desirable are described.</p>Preliminary design data package. Appendix C2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1057603/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1057603/"><img alt="Preliminary design data package. Appendix C" title="Preliminary design data package. Appendix C" src="https://digital.library.unt.edu/ark:/67531/metadc1057603/thumbnail/"/></a></p><p>The design requirements, design philosophy, method and assumptions, and preliminary computer-aided design of the Near-Term Hybrid Vehicle including its electric and heat power units, control equipment, transmission system, body, and overall vehicle characteristics are presented. (LCL)</p>Method and apparatus for aerosol-particle absorption spectroscopy. [DOE patent application]2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1053500/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1053500/"><img alt="Method and apparatus for aerosol-particle absorption spectroscopy. [DOE patent application]" title="Method and apparatus for aerosol-particle absorption spectroscopy. [DOE patent application]" src="https://digital.library.unt.edu/ark:/67531/metadc1053500/thumbnail/"/></a></p><p>A method and apparatus are described for determining the absorption spectra, and other properties, of aerosol particles. A heating beam source provides a beam of electromagnetic energy which is scanned through the region of the spectrum which is of interest. Particles exposed to the heating beam which have absorption bands within the band width of the heating beam absorb energy from the beam. The particles are also illuminated by light of a wave length such that the light is scattered by the particles. The absorption spectra of the particles can thus be determined from an analysis of the scattered light since the absorption of energy by the particles will affect the way the light is scattered. Preferably the heating beam is modulated to simplify the analysis of the scattered light. In one embodiment the heating beam is intensity modulated so that the scattered light will also be intensity modulated when the particles absorb energy. In another embodiment the heating beam passes through an interferometer and the scattered light reflects the Fourier Transform of the absorption spectra.</p>In situ instrumentation: final report of a joint EE/ME group study. [Economic utilization of oil shale, some coal deposits and geothermal resources may depend on in situ processing]2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1054405/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1054405/"><img alt="In situ instrumentation: final report of a joint EE/ME group study. [Economic utilization of oil shale, some coal deposits and geothermal resources may depend on in situ processing]" title="In situ instrumentation: final report of a joint EE/ME group study. [Economic utilization of oil shale, some coal deposits and geothermal resources may depend on in situ processing]" src="https://digital.library.unt.edu/ark:/67531/metadc1054405/thumbnail/"/></a></p><p>None</p>Preliminary proposal: fundamental combustion modeling2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1054375/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1054375/"><img alt="Preliminary proposal: fundamental combustion modeling" title="Preliminary proposal: fundamental combustion modeling" src="https://digital.library.unt.edu/ark:/67531/metadc1054375/thumbnail/"/></a></p><p>None</p>Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1059092/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1059092/"><img alt="Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections" title="Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections" src="https://digital.library.unt.edu/ark:/67531/metadc1059092/thumbnail/"/></a></p><p>The specification contains information concerning the material, process, and product requirements to be met by the fabricator. (J.R.D.)</p>Fire protection countermeasures for containment ventilation systems2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058340/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058340/"><img alt="Fire protection countermeasures for containment ventilation systems" title="Fire protection countermeasures for containment ventilation systems" src="https://digital.library.unt.edu/ark:/67531/metadc1058340/thumbnail/"/></a></p><p>The goal of this project is to find countermeasures to protect High Efficiency Particulate Air (HEPA) filters, in exit ventilation ducts, from the heat and smoke generated by fire. Initially, methods were developed to cool fire-heated air by fine water spray upstream of the filters. It was recognized that smoke aerosol exposure to HEPA filters could also cause disruption of the containment system. Through testing and analysis, several methods to partially mitigate the smoke exposure to the HEPA filters were identified. A continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. The technique is capable of protecting HEPA filters over the total time duration of the test fires. The reason for success involved the modification of the prefiltration media. Commercially available filter media has particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, rolling filter media were laminated with the desired properties. The approach was Edisonian, but truncation in short order to a combination of prefilters was effective. The application of this technique was qualified, since it is of use only to protect HEPA filters from fire-generated smoke aerosols. It is not believed that this technique is cost effective in the total spectrum of containment systems, especially if standard fire protection systems are available in the space. But in areas of high-fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified.</p>Summary of HRT Run 252018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058384/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058384/"><img alt="Summary of HRT Run 25" title="Summary of HRT Run 25" src="https://digital.library.unt.edu/ark:/67531/metadc1058384/thumbnail/"/></a></p><p>Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch in the core tank wall became dislodged, allowing greater core-to-blanket mixing. The resultant blanket uranium concentration was 2.9 g U/kg D/sub 2/O. The reactor was subsequently operated at April 28, 1961. The experiment was operated at high temperature for a total of 10,866 hours. The system was critical for a total of 8,841 hours and produced 16,295 Mwhours of power. The fuel, heavy water, and some corrosion specimens were recovered, and the reactor was stored in an assembled state. (auth)</p>Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058618/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058618/"><img alt="Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina" title="Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina" src="https://digital.library.unt.edu/ark:/67531/metadc1058618/thumbnail/"/></a></p><p>A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized bed calciner. A quantitative correlation of the effect of these variables is presented. Alumina with an intra-particle porosity as low as five per cent can be generated by employing a suitable combination of low bed temperature and dilute aluminum feed concentration. Feed sodium concentration and product alpha alumina content were found to have minor effect on intra-particle porosity. Results also show that an inverse relationship exists between the nitrate content of the calcine and the calcination temperature. (auth)</p>Estimates of post-acceleration longitudinal bunch compression2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058120/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058120/"><img alt="Estimates of post-acceleration longitudinal bunch compression" title="Estimates of post-acceleration longitudinal bunch compression" src="https://digital.library.unt.edu/ark:/67531/metadc1058120/thumbnail/"/></a></p><p>A simple analytic method is developed, based on physical approximations, for treating transient implosive longitudinal compression of bunches of heavy ions in an accelerator system for ignition of inertial-confinement fusion pellet targets. Parametric dependences of attainable compressions and of beam path lengths and times during compression are indicated for ramped pulsed-gap lines, rf systems in storage and accumulator rings, and composite systems, including sections of free drift. It appears that for high-confidence pellets in a plant producing 1000 MW of electric power the needed pulse lengths cannot be obtained with rings alone unless an unreasonably large number of them are used, independent of choice of rf harmonic number. In contrast, pulsed-gap lines alone can meet this need. The effects of an initial inward compressive drift and of longitudinal emittance are included.</p>Spectrographic Determination of Impurities in Hafnium2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1058139/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1058139/"><img alt="Spectrographic Determination of Impurities in Hafnium" title="Spectrographic Determination of Impurities in Hafnium" src="https://digital.library.unt.edu/ark:/67531/metadc1058139/thumbnail/"/></a></p><p>A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)</p>Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1052817/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1052817/"><img alt="Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre" title="Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre" src="https://digital.library.unt.edu/ark:/67531/metadc1052817/thumbnail/"/></a></p><p>An addition is presented for the IBM-7090 program MURGATROYD to produce a rough graph of reactor power versus time. A sample of output is included for the case given as an example. (J.R.D.)</p>Acoustic Emission Weld Monitoring of Nuclear Components2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1053349/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1053349/"><img alt="Acoustic Emission Weld Monitoring of Nuclear Components" title="Acoustic Emission Weld Monitoring of Nuclear Components" src="https://digital.library.unt.edu/ark:/67531/metadc1053349/thumbnail/"/></a></p><p>Acoustic emission monitoring augments other nondestructive testing methods and is sometimes applicable when other tests cannot be applied. This is, in part, due to the high sensitivity of acoustic emission monitoring. Acoustic emission monitoring is only sensitive to active flaw-growth, however, and will not detect a flaw in equilibrium. This paper describes the application of acoustic emission monitoring to nuclear reactor fuel pin end closure welds and other weldments of the reactor piping.</p>Advanced nuclear reactor public opinion project2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1053795/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1053795/"><img alt="Advanced nuclear reactor public opinion project" title="Advanced nuclear reactor public opinion project" src="https://digital.library.unt.edu/ark:/67531/metadc1053795/thumbnail/"/></a></p><p>This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.</p>Luminosity evolution at the SSC2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1053769/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1053769/"><img alt="Luminosity evolution at the SSC" title="Luminosity evolution at the SSC" src="https://digital.library.unt.edu/ark:/67531/metadc1053769/thumbnail/"/></a></p><p>A realistic'' model for the time evolution of the SSC luminosity is given. The SDC instrumentation and physics strategy should be informed by this profile. 1 ref.</p>Viewgraph notes: geologic aspects of terminal storage of radioactive wastes2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1065994/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1065994/"><img alt="Viewgraph notes: geologic aspects of terminal storage of radioactive wastes" title="Viewgraph notes: geologic aspects of terminal storage of radioactive wastes" src="https://digital.library.unt.edu/ark:/67531/metadc1065994/thumbnail/"/></a></p><p>This document contains copies of viewgraphs discussed in a presentation made at the Fifth Annual Power Conference, August 29 to September 2, 1977. No text. 19 figures, 11 references.</p>Survey of decontamination and decommissioning techniques2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1068132/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1068132/"><img alt="Survey of decontamination and decommissioning techniques" title="Survey of decontamination and decommissioning techniques" src="https://digital.library.unt.edu/ark:/67531/metadc1068132/thumbnail/"/></a></p><p>Reports and articles on decommissioning have been reviewed to determine the current technology status and also attempt to identify potential decommissioning problem areas. It is concluded that technological road blocks, which limited decommissioning facilities in the past have been removed. In general, techniques developed by maintenance in maintaining the facility have been used to decommission facilities. Some of the more promising development underway which will further simplify decommissioning activities are: electrolytic decontamination which simplifies some decontaminating operations; arc saw and vacuum furnace which reduce the volume of metallic contaminated material by a factor of 10; remotely operated plasma torch which reduces personnel exposure; and shaped charges, water cannon and rock splitters which simplify concrete removal. Areas in which published data are limited are detailed costs identifying various components included in the total cost and also the quantity of waste generated during the decommissioning activities. With the increased awareness of decommissioning requirements as specified by licensing requirements, design criteria for new facilities are taking into consideration final decommissioning of buildings. Specific building design features will evolve as designs are evaluated and implemented.</p>Hybrid simulations of quasineutral phenomena in magnetized plasma2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1067632/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1067632/"><img alt="Hybrid simulations of quasineutral phenomena in magnetized plasma" title="Hybrid simulations of quasineutral phenomena in magnetized plasma" src="https://digital.library.unt.edu/ark:/67531/metadc1067632/thumbnail/"/></a></p><p>A new class of numerical algorithms for computer simulation of low frequency electromagnetic and electrostatic phenomena in magnetized plasma is presented. Maxwell's equations are solved in the limits of quasineutrality and negligible transverse displacement current (Darwin's model). Electrons are modeled as a fluid with polarization effects ignored. Ions are described as particles. A novel feature of these algorithms is the use of the electron fluid equation of motion to determine the electric field, which renders these numerical schemes remarkably simple and direct. The simulation plasma is either periodic or bounded by particle reflecting conducting walls. Both fully nonlinear codes with spatial grids and linearized gridless codes have been implemented.</p>Pilot plant processing of sodium bifluoride to sodium fluoride pellets2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1061515/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1061515/"><img alt="Pilot plant processing of sodium bifluoride to sodium fluoride pellets" title="Pilot plant processing of sodium bifluoride to sodium fluoride pellets" src="https://digital.library.unt.edu/ark:/67531/metadc1061515/thumbnail/"/></a></p><p>Sodium fluoride (NaF) traps in the PGDP purge cascade presently use NaF pellets to remove residual UF{sub 6} from the gas stream. These pellets are procured from ORGDP which converts sodium bifluoride pellets to NaF by thermal decomposition. Discussions of the possibility of no longer producing pellets at ORGDP, due to oven corrosion problems, led to a pilot plant test at PGDP. This test was designed to examine the feasibility of producing the NaF pellets at PGDP in the event that an alternative source of supply became necessary. Satisfactory pellets were produced without difficulty; however, it was determined that the conversion process could not be readily carried out in the existing NaF traps. Construction of a separate facility with provisions to handle the large quantities of hydrogen fluoride (HF) released during the process would be required to produce pellets at the rate needed. 1 fig., 2 tabs.</p>Capacity-expansion planning under uncertainty in the electric-utility industry2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1062037/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1062037/"><img alt="Capacity-expansion planning under uncertainty in the electric-utility industry" title="Capacity-expansion planning under uncertainty in the electric-utility industry" src="https://digital.library.unt.edu/ark:/67531/metadc1062037/thumbnail/"/></a></p><p>This document basically represents a comparison between theory and practice of capacity-expansion planning in the electric-utility industry. The purpose of the comparison is to provide avenues for further exploration in utility decision making. The focus of the Phase II study is upon the role of uncertainty in the decision-making process. The Phase I effort was directed at modeling the Averch-Johnson theory of the regulated utility. Part I of this report reviews the Anderson study (D. Anderson, Models for Determining Least-Cost Investments in Electricity Supply). The Anderson paper has become a standard reference for capacity-planning studies in the electric-utility industry. Part II examines uncertainty and the behavior of the firm. Part III reviews 5 models of electric-utility capacity planning under uncertainty, and Part IV is concerned with capacity-planning models in practice.</p>10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1069911/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1069911/"><img alt="10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility" title="10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility" src="https://digital.library.unt.edu/ark:/67531/metadc1069911/thumbnail/"/></a></p><p>Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)</p>Informal Technical Progress Report and Budget for Incremental Funding2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1069879/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1069879/"><img alt="Informal Technical Progress Report and Budget for Incremental Funding" title="Informal Technical Progress Report and Budget for Incremental Funding" src="https://digital.library.unt.edu/ark:/67531/metadc1069879/thumbnail/"/></a></p><p>The principal activities during the last year were related to LAMPF experiments, a newly initiated radiochemical search for Glashow particles, and the writing up of experimental work completed at FERMILAB studying the interaction of 400-MeV protons and 150-MeV pions with complex nuclei. Collaboration is proceeding with Los Alamos on heavy methanes as atmospheric tracers and in proposing a geological search for enhanced solar neutrinos in past geological times.</p>Algebraic calculation of stroboscopic maps of ordinary, nonlinear differential equations2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1067064/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1067064/"><img alt="Algebraic calculation of stroboscopic maps of ordinary, nonlinear differential equations" title="Algebraic calculation of stroboscopic maps of ordinary, nonlinear differential equations" src="https://digital.library.unt.edu/ark:/67531/metadc1067064/thumbnail/"/></a></p><p>The relation between the parameters of a differential equation and corresponding discrete maps are becoming increasingly important in the study of nonlinear dynamical systems. Maps are well adopted for numerical computation and several universal properties of them are known. Therefore some perturbation methods have been proposed to deduce them for physical systems, which can be modeled by an ordinary differential equation (ODE) with a small nonlinearity. A new iterative, rigorous algebraic method for the calculation of the coefficients of a Taylor expansion of a stroboscopic map from ODE's with not necessarily small nonlinearities is presented. It is shown analytically that most of the coefficients are small for a small integration time and grow slowly in the course of time if the flow vector field of the ODE is polynomial and if the ODE has fixed point in the origin. Approximations of different orders respectively of the rest term are investigated for several nonlinear systems. 31 refs., 16 figs.</p>Stress analysis of ultrasonic density detector for LOFT core inlet steady-state and LOCE conditions. Supplement 12018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1067299/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1067299/"><img alt="Stress analysis of ultrasonic density detector for LOFT core inlet steady-state and LOCE conditions. Supplement 1" title="Stress analysis of ultrasonic density detector for LOFT core inlet steady-state and LOCE conditions. Supplement 1" src="https://digital.library.unt.edu/ark:/67531/metadc1067299/thumbnail/"/></a></p><p>The UDD sensor bar with modified cross-section (0.0938-in. thick by 0.25-in. high overall) was analyzed to determine its resonant frequencies. Thermal and fluid-induced stresses due to steady-state and LOCE loads were also calculated. The sensor bar was shown not to be subject to vortex-shedding lock-in and was shown to meet applicable criteria of the ASME Boiler and Pressure Vessel Code. Seismic loads are insignificant compared to fluid loads.</p>GAMIDEN: a program to aid in the identification of unknown materials by gamma-ray spectroscopy2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1060970/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1060970/"><img alt="GAMIDEN: a program to aid in the identification of unknown materials by gamma-ray spectroscopy" title="GAMIDEN: a program to aid in the identification of unknown materials by gamma-ray spectroscopy" src="https://digital.library.unt.edu/ark:/67531/metadc1060970/thumbnail/"/></a></p><p>The intent of the computer code GAMIDEN is to help identify isotopes by their gamma-ray emissions and thus to assist in the nondestructive assay of unknown materials. From both radioactive decays and neutron captures, GAMIDEN searches GAMTOT78, a file of gamma-ray spectra, for matches with observed photon energies. This report describes the search procedure, outlines the use of the code, and gives an example. The code is designed to operate on the CRAY 1 computer at Lawrence Livermore National Laboratory (LLNL). It is written in standard Fortran (ANSI) for the most part but contains some LRLTRAN instructions to make use of the Livermore time-sharing system (LTSS). The code uses about 545,000 words of memory. Typical problems run in about 45 s. The source program and the data file are available on request.</p>Results of TMX operations: January-July 19802018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1061642/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1061642/"><img alt="Results of TMX operations: January-July 1980" title="Results of TMX operations: January-July 1980" src="https://digital.library.unt.edu/ark:/67531/metadc1061642/thumbnail/"/></a></p><p>This interim report summarizes results from the Tandem Mirror Experiment (TMX) during the period January to July 1980 and describes the physics experiments, the machine operation, and the diagnostics that were added to TMX during this period. This operating period followed the initial proof-of-principle TMX experiments and predated the ongoing final experiments preceding TMX shutdown for modification to TMX Upgrade. The results described in this report include measurements of plasma parameters and plasma behavior which confirm the initial TMX results that demonstrated that the tandem mirror configuration can be generated and sustained by neutral beam injection and that the tandem mirror configuration improves confinement of magnetic mirror systems.</p>A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 19622018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1060506/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1060506/"><img alt="A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962" title="A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962" src="https://digital.library.unt.edu/ark:/67531/metadc1060506/thumbnail/"/></a></p><p>The effect of modifying the dislocation structure by room-temperature prestraining on the subsequent yielding behavior at 77 deg K is being studied. Results on tantalum single crystals indicated that a considerable decrease in the early yield stress for a given strain is effected by prestraining at room temperature. Twinning was observed in the tantalum at 77 deg K and normal rates of strain. It is shown that the potential barrler to dislocation motion in crystalline solids can be measured in relatively pure bcc transition metals such as Nb, Ta, Mo, and W. Work is being carried out to extend the method of differential calorimetry to measurements of stored-energy-release spectra in deformed bcc metals. Measurements for copper are discussed. (M.C.G.)</p>Hybrid charged-particle guide for studying (n, charged particle) reactions2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1060460/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1060460/"><img alt="Hybrid charged-particle guide for studying (n, charged particle) reactions" title="Hybrid charged-particle guide for studying (n, charged particle) reactions" src="https://digital.library.unt.edu/ark:/67531/metadc1060460/thumbnail/"/></a></p><p>Charged-particle transport systems consisting of magnetic quadrupole lenses have been employed in recent years in the study of (n, charged particle) reactions. We have completed a new transport system that is based both on magnetic lenses as well as electrostatic fields. The magnetic focusing of this charged-particle guide is provided by six magnetic quadrupole lenses arranged in a CDCCDC sequence (in the vertical plane). The electrostatic field is produced by a wire at high voltage which stretches the length of the guide and is physically at the center of the magnetic axis. The magnetic lenses are used for charged particles above 5 MeV; the electrostatic guide is used for lower energies. This hybrid system possesses the excellent focusing and background rejection properties of other magnetic systems. For low energy charged-particles, the electrostatic transport avoids the narrow band-passes in charged-particle energy which are a problem with purely magnetic transport systems. This system is installed at the LLNL Cyclograaff facility for the study of (n, charged particle) reactions at neutron energies up to 35 MeV.</p>Measurements of surface ocean carbon dioxide partial pressure during WOCE2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1065067/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1065067/"><img alt="Measurements of surface ocean carbon dioxide partial pressure during WOCE" title="Measurements of surface ocean carbon dioxide partial pressure during WOCE" src="https://digital.library.unt.edu/ark:/67531/metadc1065067/thumbnail/"/></a></p><p>Progress during the past year of research under Measurements of Surface Ocean Carbon Dioxide Partial Pressure During WOCE'' has been significant. As was described in our previous progress report, the startup phase of this research was severely frustrated by delays in the US WOCE Hydrographic Program (WHP), which in turn were caused by delays in the mid-life refit of the R/V Knorr. As a result the high latitude southeastern Pacific work (WHP lines P19S and P16S) originally scheduled for the 1990 austral summer has still not been carried out. As a substitute, the smaller R/V Thomas Washington was pressed into service during mid-1991 to carry out lower-latitude portions of the WHP P16 and P17 lines - the TUNES Expedition. Because this ship is much smaller than the R/V Knorr, she could not carry a full complement of WHP programs and seagoing personnel and was restricted by her size and the time of year to lower-latitude work. Our original proposal for carbon dioxide measurements was designed to divide the work between legs in which we participated as part of the WHP dissolved CFC program (under separate NSF funding) and legs in which we entrusted the operation of our system to other CFC or carbon dioxide laboratories with expertise in gas chromatography. Since we were not involved in any CFC work on the substituted Washington expedition, and since all the seagoing programs on the Washington were additionally stressed by a shortage of people and space, this placed our carbon dioxide program at an unwelcome disadvantage. The preliminary results for carbon dioxide and nitrous oxide are shown. We are forced to rely on spotty manual observations and station CTD temperatures to reconstruct our equilibrator temperature solubility corrections for portions of that leg. We did not get our usual reliable data return, but the results were surely worth effort, especially for this vast and rarely-visited region of the world oceans.</p>Heavy metal contamination in TIMS Branch sediments2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1065143/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1065143/"><img alt="Heavy metal contamination in TIMS Branch sediments" title="Heavy metal contamination in TIMS Branch sediments" src="https://digital.library.unt.edu/ark:/67531/metadc1065143/thumbnail/"/></a></p><p>The objective of this memorandum is to summarize results of previous sediment studies on Tims Branch and Steed's Pond conducted by Health Protection (HP) and by the Savannah River Laboratory (SRL) in conjunction with Reactor Materials Engineering Technology (RMET). The results for other heavy metals, such as lead, nickel, copper, mercury, chromium, cadmium, zinc, and thorium are also summarized.</p>Status report: waste incineration and fixation for Waste Management, Production, and Reprocessing Division of the Department of Energy (July--December 1976)2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1064763/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1064763/"><img alt="Status report: waste incineration and fixation for Waste Management, Production, and Reprocessing Division of the Department of Energy (July--December 1976)" title="Status report: waste incineration and fixation for Waste Management, Production, and Reprocessing Division of the Department of Energy (July--December 1976)" src="https://digital.library.unt.edu/ark:/67531/metadc1064763/thumbnail/"/></a></p><p>Fluidized bed incineration and waste fixation processes are being used to process the types of wastes expected from nuclear fuel reprocessing and production plants. Test incineration runs have been made on two types of wastes: high efficiency particulate air (HEPA) filters and tributyl phosphate-solvent solutions. Laboratory-scale vitrification equipment was used to produce glass pellets from incinerator ash and blends of other expected waste streams. Computer modeling gave an expected product integrity life of over 2,000 years.</p>Measurement and Modeling of Advanced Coal Conversion Processes2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1069297/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1069297/"><img alt="Measurement and Modeling of Advanced Coal Conversion Processes" title="Measurement and Modeling of Advanced Coal Conversion Processes" src="https://digital.library.unt.edu/ark:/67531/metadc1069297/thumbnail/"/></a></p><p>The objectives of this study are to establish the mechanisms and rates of basic steps in coal conversion processes, to integrate and incorporate this information into comprehensive computer models for coal conversion processes, to evaluate these models and to apply them to gasification, mild gasification and combustion in heat engines. (VC)</p>Evaluation of cracking in feedwater piping adjacent to the steam generators in Nine Pressurized Water Reactor Plants2018-02-04T10:51:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1069664/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1069664/"><img alt="Evaluation of cracking in feedwater piping adjacent to the steam generators in Nine Pressurized Water Reactor Plants" title="Evaluation of cracking in feedwater piping adjacent to the steam generators in Nine Pressurized Water Reactor Plants" src="https://digital.library.unt.edu/ark:/67531/metadc1069664/thumbnail/"/></a></p><p>Cracking in ASTM A106-B and A106-C feedwater piping was detected near the inlet to the steam generators in a number of pressurized water reactor plants. We received sections with cracks from nine of the plants with the objective of identifying the cracking mechanism and assessing various factors that might contribute to this cracking. Variations were observed in piping surface irregularities, corrosion-product, pit, and crack morphology, surface elmental and crystal structure analyses, and steel microstructures and mechanical properties. However, with but two exceptions, namely, arrest bands and major surface irregularities, we were unable to relate the extent of cracking to any of these factors. Tensile and fracture toughness (J/sub Ic/ and tearing modulus) properties were measured over a range of temperatures and strain rates. No unusual properties or microstructures were observed that could be related to the cracking problem. All crack surfaces contained thick oxide deposits and showed evidence of cyclic events in the form of arrest bands. Transmission electron microscopy revealed fatigue striations on replicas of cleaned crack surfaces from one plant and possibly from three others. Calculations based on the observed striation spacings gave a value of ..delta..sigma = 150 MPa (22 ksi) for one of the major cracks. The direction of crack propagation was invariably related to the piping surface and not to the piping axis. These two factors are consistent with the proposed concept of thermally induced, cyclic, tensile surface stresses. Although surface irregularities and corrosion pits were sources for crack initiation and corrosion may have contributed to crack propagation, it is proposed that the overriding factor in the cracking problem is the presence of unforeseen cyclic loads.</p>Quadric solids and computational geometry2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1060645/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1060645/"><img alt="Quadric solids and computational geometry" title="Quadric solids and computational geometry" src="https://digital.library.unt.edu/ark:/67531/metadc1060645/thumbnail/"/></a></p><p>As part of the CAD-CAM development project, this report discusses the mathematics underlying the program QUADRIC, which does computations on objects modeled as Boolean combinations of quadric half-spaces. Topics considered include projective space, quadric surfaces, polars, affine transformations, the construction of solids, shaded image, the inertia tensor, moments, volume, surface integrals, Monte Carlo integration, and stratified sampling. 1 figure.</p>Numerical simulation of the stability in a cable-in-conduit conductor developed for fusion-magnet applications2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1060148/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1060148/"><img alt="Numerical simulation of the stability in a cable-in-conduit conductor developed for fusion-magnet applications" title="Numerical simulation of the stability in a cable-in-conduit conductor developed for fusion-magnet applications" src="https://digital.library.unt.edu/ark:/67531/metadc1060148/thumbnail/"/></a></p><p>The stability margins of the US-Demonstration Poloidal Coil (US-DPC) and the International Thermonuclear Experimental Reactor (ITER) TF coils have been modeled numerically using the computer program CICC. The computed US-DPC limiting current, I{sub lim}, compares favorably with the values determined experimentally. Using the detailed program CICC output, we investigated the DPC quench initiation mechanism in each of the three stability regions. In the ill-cooled region, the imposed heat pulse heats the conductor to the current-sharing temperature, T{sub cs}. In the transition region, the resistance heating after the pulse must be strong enough to overcome the induced flow reversal. In the well-cooled region, good heat transfer heats the helium during the pulse. After the pulse, these high helium temperatures along with poor heat transfer cause the conductor to quench. Changes in I{sub lim} agree with Dresner's relationship. I{sub lim} can be improved by decreasing the copper resistivity, the helium fraction, or the conductor diameter. Preliminary results show the ITER and TF coil operating point is in the well-cooled region. 10 refs., 7 figs., 1 tab.</p>