Partner
Oklahoma Historical Society
7,553
UNT Libraries Special Collections
5,302
UNT Libraries Government Documents Department
5,269
Texas Historical Commission
2,053
UNT Libraries
560
Dallas Museum of Art
326
Sterling Municipal Library
320
Cooke County Library
297
UNT Music Library
248
Carl Albert Congressional Research and Studies Center
206
177 More
Collection
Oklahoma Publishing Company Photography Collection
5,115
Texas Digital Newspaper Program
4,556
Office of Scientific & Technical Information Technical Reports
4,016
KXAS-NBC 5 News Collection
2,830
Oklahoma Digital Newspaper Program
2,289
Tocker Foundation Grant
2,047
THC National Register Collection
1,957
LGBT Collections
1,521
The Dallas Metroplex Chapter of the Names Project Foundation Collection
930
Texas State Publications
485
313 More
Degree Department
Degree Discipline
Degree Level
Country
States
Year
Month
Thermophysical properties of argon
The entire report consists of tables of thermodynamic properties (including sound velocity, thermal conductivity and diffusivity, Prandtl number, density) of argon at 86 to 400/degree/K, in the form of isobars over 0.9 to 100 bars. (DLC)
Date:
February 1, 1988
Creator:
Jaques, A.
Object Type:
Report
System:
The UNT Digital Library
Sources of polarized ions and atoms
In this presentation we discuss methods of producing large quantities of polarized atoms and ions (Stern-Gerlach separation, optical pumping, and spin-exchange) as well as experimental methods of measuring the degree of polarization of atomic systems. The usefulness of polarized atoms in probing the microscopic magnetic surface properties of materials will also be discussed. 39 refs., 5 figs., 2 tabs.
Date:
January 1, 1988
Creator:
Cornelius, W.D.
Object Type:
Article
System:
The UNT Digital Library
Background radiation from fission pulses
Extensive source terms for beta, gamma, and neutrons following fission pulses are presented in various tabular and graphical forms. Neutron results from a wide range of fissioning nuclides (42) are examined and detailed information is provided for four fuels: /sup 235/U, /sup 238/U, /sup 232/Th, and /sup 239/Pu; these bracket the range of the delayed spectra. Results at several cooling (decay) times are presented. For ..beta../sup -/ and ..gamma.. spectra, only /sup 235/U and /sup 239/Pu results are given; fission-product data are currently inadequate for other fuels. The data base consists of all known measured data for individual fission products extensively supplemented with nuclear model results. The process is evolutionary, and therefore, the current base is summarized in sufficient detail for users to judge its quality. Comparisons with recent delayed neutron experiments and total ..beta../sup -/ and ..gamma.. decay energies are included. 27 refs., 47 figs., 9 tabs.
Date:
May 1, 1988
Creator:
England, T. R.; Arthur, E. D.; Brady, M. C. & LaBauve, R. J.
Object Type:
Report
System:
The UNT Digital Library
Field characterization and personal dosimetry at a high energy ion accelerator
The response of a variety of dosimeters was evaluated in the radiation field outside the shielding of the Lawrence Berkeley Laboratory Bevalac Biomedical Facility. The primary beam was 580 MeV/center dot/A neon ions, incident upon a 30.5-cm polyethylene cube. The field was characterized by a neutron spectrometer consisting of Bonner spheres and other detectors and by estimates of charged particle fluences in NTA film and in the Berklet spectrometer. The responses of American Acrylics CR-39 track-etch plastic detectors and AECL (Canada) type BD-100 Bubble Detectors were compared to those of NTA film, Andersson-Braun remmeter and recombination-chamber results as well as to reference dose equivalents based upon the unfolded neutron spectrum. Evaluations of these dosimeters are discussed. 7 refs., 4 figs.
Date:
March 1, 1988
Creator:
Greenhouse, N. A.; Busick, D. D.; de Castro, T. M.; Elwyn, A. J.; Hankins, D. E.; Ipe, N. E et al.
Object Type:
Article
System:
The UNT Digital Library
Permeability damage to natural fractures caused by fracturing fluid polymers
Formation damage studies using artificially fractured, low-permeability sandstone cores indicate that viscosified fracturing fluids can severely restrict gas flow through these types of narrow fractures. These studies were performed in support of the Department of Energy's Multiwell Experiment (MWX). Extensive geological and production evaluations at the MWX site indicate that the presence of a natural fracture system is largely responsible for unstimulated gas production. The laboratory formation damage studies were designed to examine changes in cracked core permeability to gas caused by fracturing fluid residues introduced into such narrow fractures during fluid leakoff. Polysaccharide polymers caused significant reduction (up to 95%) to gas flow through cracked cores. Polymer fracturing fluid gels used in this study included hydroxypropyl guar, hydroxyethyl cellulose, and xanthan gum. In contrast, polyacrylamide gels caused little or no reduction in gas flow through cracked cores after liquid cleanup. Other components of fracturing fluids (surfactants, breakers, etc.) caused less damage to gas flows. Other factors affecting gas flow through cracked cores were investigated, including the effects of net confining stress and non-Darcy flow parameters. Results are related to some of the problems observed during the stimulation program conducted for the MWX. 24 refs., 4 figs., 7 tabs.
Date:
April 1, 1988
Creator:
Gall, B. L.; Sattler, A. R.; Maloney, D. R. & Raible, C. J.
Object Type:
Article
System:
The UNT Digital Library
Coarse-node computations with an adaptive node structure
The analysis with COMMIX of liquid metal reactor (LMR) intermediate heat exchanger (IHX) transients that are characterized by low flows, and especially imbalanced low flows, shows that if a coarse-node structure is used the predicted temperatures are significantly different than those given by a fine-node structure. If a fine-node structure is used, for problems that involve a large part of the plant, the computation time becomes excessive. This paper presents an improved version of an adaptive node structure. At this stage this version has been applied only to one-dimensional problems.
Date:
January 1, 1988
Creator:
Tzanos, C.P.
Object Type:
Article
System:
The UNT Digital Library
Transient thermal analysis of three fast-charging latent heat storage configurations for a space-based power system
A space-based thermal storage application must accept large quantities of heat in a short period of time at an elevated temperature. A model of a lithium hydride phase change energy storage system was used to estimate reasonable physical dimensions for this application which included the use of a liquid metal heat transfer fluid. A finite difference computer code was developed and used to evaluate three methods of enhancing heat transfer in the PCM energy storage system. None of these three methods, inserting thin fins, reticulated nickel, or liquid lithium, significantly improved the system performance. The use of a 95% void fraction reticulated nickel insert was found to increase the storage capacity (total energy stored) of the system slightly with only a small decrease in the system energy density (energy storage/system mass). The addition of 10% liquid lithium was found to cause minor increases in both storage density and storage capacity with the added benefit of reducing the hydrogen pressure of the lithium hydride. 9 refs., 7 figs., 2 tabs.
Date:
January 1, 1988
Creator:
Stovall, T. K. & Arimilli, R. V.
Object Type:
Article
System:
The UNT Digital Library
Full-wave calculations in flux coordinates for toroidal geometry
A new 2-D full-wave code, HYPERION, employing a poloidal and toroidal mode expansion and including the toroidal terms arising in the wave equation has been developed. It is based on the existing modules developed for the MHD stability codes and uses as input the tokamak equilibria calculated with the RSTEQ code. At present the plasma response is described by the collisionally broadened cold plasma conductivity. However, the code is written in straight field line coordinates, this permits the accurate representation of k /sub /parallel// and as a consequence allows the incorporation of the plasma Z functions. This code also retains the E/sub /parallel// component of the electric field which will allow the study of the low density region of the plasma. We have done detailed benchmarking of the HYPERION code in the cold plasma limit with the existing finite difference ORION full-wave code. The agreement is very good.
Date:
January 1, 1988
Creator:
Carreras, B. A.; Lynch, V. E.; Jaeger, E. F. & Batchelor, D. B.
Object Type:
Article
System:
The UNT Digital Library
Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution
A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were performed with an array of mixed oxide fuel pins in aqueous plutonium-uranium solutions. The fuel pins were contained in a boiler tube-type tank and arranged in a 1.4 cm square pitch array which resembled cylindrical geometry. One experiment was perfomed with the fuel pins removed from the vessel. The experiments were performed with a water reflector. The concentration of the solutions in the boiler tube-type tank was varied from 4 to 468 g (Pu + U)/liter. The ratio of plutonium to total heavy metal (plutonium plus uranium) was approximately 0.22 for all experiments.
Date:
August 1, 1988
Creator:
Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))
Object Type:
Report
System:
The UNT Digital Library
A one-and-a-quarter-dimensional transport code for field-reversed configuration studies: A user's guide for CFRX
A one-and-a-quarter-dimensional transport code, which includes radial as well as some two-dimensional effects for field-reversed configurations, is described. The set of transport equations is transformed to a set of new independent and dependent variables and is solved as a coupled initial-boundary value problem. The code simulation includes both the closed and open field regions. The axial effects incorporated include global axial force balance, axial losses in the open field region, and flux surface averaging over the closed field region. Input, output, and structure of the code are described in detail. A typical example of the code results is also given. 20 refs., 21 figs., 7 tabs.
Date:
May 1, 1988
Creator:
Hsiao, Ming-Yuan; Werley, K.A. & Ling, Kuok-Mee
Object Type:
Report
System:
The UNT Digital Library
A Search for New Leptons with Heavy Neutrinos in e/sup +/e/sup -/ Annihilation at. sqrt. s = 29 GeV. [None]
This thesis describes the results of a search for new leptons with associated heavy neutrinos. The search uses 68.1 pb/sup /minus/1/ of data taken with the TPC2..gamma.. detector at the PEP storage ring. New lepton pairs with charged lepton masses m/sub L/ < 12 GeV and mass differences in the approximate range 0.4 GeV < m/sub L/ /minus/ m/sub/nu/L/ < 2.5 GeV are excluded at the 99% confidence level. Results are also given of a study of search techniques for the region m/sub L/ < 12 GeV, m/sub L/ /minus/ m/sub ..nu..L/ < 0.4 GeV.
Date:
May 5, 1988
Creator:
Mathis, L. G.
Object Type:
Report
System:
The UNT Digital Library
Hyperdeformed nuclei and the residual pseudo-SU(3) symmetry
The author discusses superdeformed and hypothetical hyperdeformed nuclei. Quadrupole deformations characteristic of these types of nuclei are defined. Symmetry features are also discussed. The characteristic cycle dependence of shell structures as functions of the deformation gives rise to chains of the deformed shell closures. Such a chain structure applies to moderately-, super- and hyper-deformed nuclei as well. The resulting total energy calculations give a systematic variation of super- and hyperdeformations with, e.g., increasing N at fixed Z, thus predicting the way nuclei deviate from the simple a:b = 2:1 and a:b = 3:1 symmetries.
Date:
January 1, 1988
Creator:
Dudek, J. & Werner, T.
Object Type:
Article
System:
The UNT Digital Library
The solar flare of 18 August 1979: Incoherent scatter radar data and photochemical model comparisons
Measurements of electron density at seven D-region altidues were made with the Arecibo radar during a Class-X solar flare on 18 August 1979. Measurements of solar x-ray fluxes during the same period were available from the GOES-2 satellite (0.5 to 4 /angstrom/ and 1 to 8 /angstrom/) and from ISEE-3 (in four bands between 26 and 400 keV). From the x-ray flux data we computed ionization rates in the D-region and the associated chemical changes, using a coupled atmospheric chemistry and diffusion model (with 836 chemical reactions and 19 vertical levels). The computed electron densities matched the data fairly well after we had adjusted the rate coefficients of two reactions. We discuss the hierarchies among the many flare-induced chemical reactions in two altitude ranges within the D-region and the effects of adjusting several other rate coefficients. 51 refs., 6 figs., 3 tabs.
Date:
April 1, 1988
Creator:
Zinn, J.; Sutherland, C. D.; Fenimore, E. E. & Ganguly, S.
Object Type:
Report
System:
The UNT Digital Library
Conservation and Renewable Energy Program: Bibliography, 1988 edition
The 831 references covering the period 1980 through Feb. 1988, are arranged under the following: analysis and evaluation, building equipment, building thermal envelope systems and materials, community systems and cogeneration, residential conservation service, retrofit, advanced heat engine ceramics, alternative fuels, microemulsion fuels, industrial chemical heat pumps, materials for waste heat utilization, energy conversion and utilization materials, tribology, emergency energy conservation,inventions, electric energy systems, thermal storage, biofuels production, biotechnology, solar technology, geothermal, and continuous chromatography in multicomponent separations. An author index is included.
Date:
April 1, 1988
Creator:
Vaughan, K.H. (comp.)
Object Type:
Report
System:
The UNT Digital Library
Niagara Falls Storage Site, Lewiston, New York: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)
The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1987 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 13 refs., 10 figs., 20 tabs.
Date:
April 1, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Passive safety and the advanced liquid metal reactors
Advanced Liquid Metal Reactors being developed today in the USA are designed to make maximum use of passive safety features. Much of the LMR safety work at Argonne National Laboratory is concerned with demonstrating, both theoretically and experimentally, the effectiveness of the passive safety features. The characteristics that contribute to passive safety are discussed, with particular emphasis on decay heat removal systems, together with examples of Argonne's theoretical and experimental programs in this area.
Date:
January 1, 1988
Creator:
Hill, D.J.; Pedersen, D.R. & Marchaterre, J.F.
Object Type:
Article
System:
The UNT Digital Library
Ultraviolet imaging of hydrogen flames
We have assembled an ultraviolet-sensitive intensified camera for observing hydrogen combustion by imaging the OH, A/sup 2/..sigma.. - X/sup 2//Pi/ bandhead emissions near 309 nm. The camera consists of a quartz and CaF achromat lense-coupled to an ultraviolet image intensifier which is in turn fiber-coupled to a focus projection scan (FPS) vidicon. The emission band is selected with interference filters which serve to discriminate against background. The camera provides optical gain of 100 to 1000 and is capable of being shuttered at nanosecond speeds and of being framed at over 600 frames per second. We present data from observations of test flames in air at standard RS-170 video rates with varying background conditions. Enhanced images using background subtraction are presented. Finally, we discuss the use of polarizaton effects to further discrimination against sky background. This work began as a feasibility study to investigate ultraviolet technology to detect hydrogen fires for the NASA space program. 6 refs., 7 figs, 2 tabs.
Date:
January 1, 1988
Creator:
Yates, G. J.; Wilke, M. & King, N.
Object Type:
Article
System:
The UNT Digital Library
The safety record at the tritium systems test assembly
This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary tritium piping in a controlled environment, an efficient, all-purpose tritium waste-treatment plant with 100% availability, and ultrasensitive, real-time diagnostics for anticipating and preventing releases, and for detection and location of tritium leaks in a low-risk mode. 5 refs., 11 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Coffin, D.O.
Object Type:
Article
System:
The UNT Digital Library
Methods and techniques of NDA (nondestructive assay)
Nondestructive assay (NDA) refers to techniques and instruments developed to measure nuclear materials in the many forms in which they occur throughout the fuel cycle. These techniques were first developed to support nuclear safeguards inspections and nuclear material accountability; they are also used extensively for process and quality control. Most accountability measurements are based on analytical chemistry and require that a sample be drawn and analyzed destructively. Destructive analysis can not be applied to many of the product materials found in the fuel cycle, such as fuel rods and assemblies, because of their high monetary value. Also, many waste and scrap materials can not be adequately sampled for destructive analysis because of their heterogenous nature. This situation led to the development of nondestructive analysis techniques. This paper presents an overview of the major NDA techniques and instrumentation in use today. The instrumentation described below is now used frequently by safeguards inspectors and facility operators alike. 19 refs., 18 figs., 4 tabs.
Date:
January 1, 1988
Creator:
Reilly, T. D.
Object Type:
Article
System:
The UNT Digital Library
Blanket technology experiments at Argonne National Laboratory
Argonne National Laboratory has the largest US program for the development of blanket technology. The goals of the program are to resolve critical issues for different blanket concepts, to develop the understanding and predictive capability of blanket behavior, and to develop the technology needed to build and operate advanced fusion blankets. The projects within the program are liquid metal MHD, breeder neutronics, tritium oxidation, transient electromagnetics, FLIBE chemistry, and insulator coatings. The present status and recent results of the projects are described.
Date:
February 1, 1988
Creator:
Mattas, R. F.; Reed, C. B.; Picologlou, B.; Finn, P.; Clemmer, R.; Porges, K. et al.
Object Type:
Article
System:
The UNT Digital Library
Development and process evaluation of improved Fischer-Tropsch slurry catalysts
The objective of this contract is to develop a consistent technical data base on the use of iron-based catalysts in Fischer-Tropsch (FT) synthesis reactions. This data base will be developed to allow the unambiguous comparison of the performance of these catalysts with each other and with state-of-the-art iron catalyst comparisons. Particular attention will be devoted to generating reproducible kinetic and selectivity data and to developing reproducible improved catalyst compositions.
Date:
January 1, 1988
Creator:
Withers, H.P. (Air Products and Chemicals, Inc., Allentown, PA (United States)); Bukur, D.B. & Rosynek, M.P. (Texas A and M Univ., College Station, TX (United States))
Object Type:
Report
System:
The UNT Digital Library
Monitoring the materials and chemistry of a geothermal plant
The components of geothermal brines that cause corrosion and scaling problems are reviewed, especially brine pH, CO/sub 2/, H/sub 2/S, oxygen (from air), silicia, calcium, sulfides, and suspended particulates. Instrumental methods for on-line measurement are discussed to show how to keep costs low by operating a geothermal plant from a position of knowledge of what is occurring to the plant materials. The US Department of Energy research and development program in brine chemistry and on-line instrument development at Pacific Northwest Laboratory is discussed along with the strategy for commercial availability of new instruments to the geothermal industry.
Date:
April 1, 1988
Creator:
Shannon, D.W.
Object Type:
Article
System:
The UNT Digital Library
Project to design and develop an energy-related program: For public housing residents and renters: Volume 1, Final report
This demonstration project was undertaken as a result of an unsolicited proposal submitted by THE ASSIGNMENT GROUP (TAG) to the Office of Minority Economic Impact, Department of Energy (DOE). The problem to which the proposal responded was how to minimize the costs associated with public housing tenants in standard public housing as well as under homeownership transfers. A related problem was how to graduate the tenants to another level of responsibility and self-sufficiency through resident business developments and training in energy-related fields. The size and gravity of the problem necessitated a purpose or aim that had nationwide application, yet lent itself to a microscopic look. Consequently, the goal that emanated was the design and development of an energy-related demonstration program that educates public housing residents, facilitates indigenous business development where appropriate, and trains residents to provide needed services.
Date:
May 1, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Benefits of vertical and horizontal seismic isolation for LMR (liquid metal reactor) nuclear reactor units
Seismic isolation has been shown to be able to reduce transmitted seismic force and lower response accelerations of a structure. When applied to nuclear reactors, it will minimize seismic influence on the reactor design and provide a design which is less site dependent. In liquid metal reactors where components are virtually at atmospheric pressure but under severe thermal conditions, thin-walled structures are generally used for primary systems. Thin-walled structures, however, have little inherent seismic resistance. The concept of seismic isolation therefore offers a viable and effective approach that permits the reactor structures to better withstand thermal and seismic loadings simultaneously. The majority of published work on seismic isolation deals with use of horizontal isolation system only. In this investigation, however, local vertical isolation is also provided for the primary system. Such local vertical isolation is found to result in significant benefits for major massive components, such as the reactor cover, designed to withstand vertical motions and loadings. Preliminary estimations on commodity savings of the primary system show that, with additional local vertical isolation, the savings could be twice that estimated for horizontal isolation only. The degree of effectiveness of vertical isolation depends on the diameter of the reactor vessel. As …
Date:
January 1, 1988
Creator:
Wu, Ting-shu; Chang, Y. W. & Seidensticker, R. W.
Object Type:
Article
System:
The UNT Digital Library