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[Photograph 2012.201.TP0392.0569]

Photograph used for a newspaper owned by the Oklahoma Publishing Company. Caption: "Geologists estimate that the oil in he oil shale of western Colorado could supply he country for 500 years."
Date: June 27, 1979
Creator: 3rd Party
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.TP0392.0935]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Portable generator is moved into place so that Oklahoma Natural Gas Co. 's emergency communication vehicle, a 25-foot trailer, can operate Independently of local power should it be necessary during an outage anywhere in OGN's operating territory."
Date: 1979
Creator: 3rd Party
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0119A.0612]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Sid Caesar , actor."
Date: 1979
Creator: ABC Network
Object Type: Photograph
System: The Gateway to Oklahoma History
Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program primarily for the Rocky Mountain states of New Mexico, Colorado, Wyoming, and Montana, and the State of Alaska. Semiannual progress report, October 1978-March 1979 (open access)

Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program primarily for the Rocky Mountain states of New Mexico, Colorado, Wyoming, and Montana, and the State of Alaska. Semiannual progress report, October 1978-March 1979

During this six-month period, Hydrogeochemical and Stream Sediment Reconnaissance samples were collected by the Los Alamos Scientific Laboratory (LASL) from 623 locations in Colorado for a special study. Additional special studies are planned for nine other areas in the Rocky Mountain states in fiscal year 1979, plus some cleanup reconnaissance sampling in parts of four quadrangles that overlap state borders. Preparations for reconnaissance sampling of the entire North Slope region of Alaska have been made but sampling is contingent upon receiving supplemental funds. Water samples from 6725 locations were analyzed for uranium by fluorometry or delayed-neutron counting (DNC). Water samples from 9390 locations were analyzed by emission spectroscopy for 12 other elements. Sediment samples from 14,414 locations were analyzed for uranium and 31 other elements by combined DNC and neutron activation analysis. Sediment samples from 9876 locations were analyzed for two additional elements by x-ray fluorescence. Nine LASL reconnaissance reports, one pilot study data release, one supplemental multielement data release, a multielement data release for three areas in western Alaska, and one quarterly report were open filed by the Department of Energy, Grand Junction Office during the six-month period. Numerous other reports are in various stages of completion and several …
Date: July 1, 1979
Creator: Aamodt, P. L.; Bunker, M. E.; Waterbury, G. R. & Waller, R. A.
Object Type: Report
System: The UNT Digital Library
Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the McGrath and Talkeetna NTMS Quadrangles, Alaska, Including Concentrations of Forty-Three Additional Elements (open access)

Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the McGrath and Talkeetna NTMS Quadrangles, Alaska, Including Concentrations of Forty-Three Additional Elements

From abstract: During the summer of 1977, 1268 water and 1206 sediment samples were collected from 1292 lakes and streams throughout the 33 600-km2 area within the boundaries of the McGrath and Talkeetna National Topographic Map Series quadrangles in south-central Alaska. Each of the water samples was analyzed for uranium and 12 other elements, and each of the sediment samples was analyzed for uranium, thorium, and 41 other elements. All of the field and analytical data are listed in appendixes to this report, but only the uranium and thorium data are discussed herein.
Date: April 1979
Creator: Aamodt, Paul L.; Jacobsen, Sue Israel & Hill, Dwight E.
Object Type: Report
System: The UNT Digital Library
Development of cermets for high level radioactive waste fixation (open access)

Development of cermets for high level radioactive waste fixation

A method for the solidification and fixation of commercial and defense high-level radioactive wastes, namely a cermet process, is currently under development. Chemical and physical processing techniques, as developed up to this time, and the subsequent properties of the resulting cermet bodies are described; unique and advantageous features of the cermet waste form and the conversion process are discussed.
Date: January 1, 1979
Creator: Aaron, W S; Quinby, T C & Kobisk, E H
Object Type: Article
System: The UNT Digital Library
Development and characterization of cermet forms for radioactive waste (open access)

Development and characterization of cermet forms for radioactive waste

Cermets designed to isolate high-level wastes in a solid form are a composite consisting of various ceramic phase particles uniformly dispersed in and microencapsulated by an iron-nickel base alloy matrix. The metal matrix provides this waste form with many advantageous features including excellent thermal conductivity and mechanical strength. These cermets are formed by first dissolving the waste in molten urea, precipitating and calcining all the constituents, compacting the calcine, and sintering and reduction to form the final product. The exact formulation of cermets through additions to the waste is designed to fix most of the fission products in stable, leach resistant ceramic phases which are subsequently microencapsulated by an alloy matrix. The alloy matrix, which is derived primarily from the waste itself and includes the reducible fission and activation products from the waste, can be compositionally adjusted through additions to optimize its corrosion resistance under conditions existing in various disposal environments. The processes by which cermets are formed include several new and unique materials preparation options that are being developed to permit engineering scale-up and to be compatible with remote operations. Cermets formed by alternate processing methods are being characterized. Initially, cermet samples were prepared using a laboratory scale, batch …
Date: January 1, 1979
Creator: Aaron, W. S.; Quinby, T. C. & Kobisk, E. H.
Object Type: Article
System: The UNT Digital Library
Soviet Oil Politics and the Middle East (open access)

Soviet Oil Politics and the Middle East

This investigation, covering the past two decades, attempts to determine what benefits the Soviets have sought to gain in their relationships with Middle Eastern oil-producing nations. Chapter I surveys the U.S.S.R.'s oil industry and its tentative prospects for the 1980's. Chapter II discusses Soviet involvement in the Middle East since 1950, including nationalization and oil embargoes. In Chapter III, developments less favorable to the U.S.S.R. are, analyzed: the growing influence of conservative, anti -Soviet oil-producing states and the deradicalization of other Middle Eastern nations. Chapter IV concludes that the Soviets have met with varying success in their Middle Eastern involvements. The future of their oil industry remains uncertain.
Date: December 1979
Creator: Abbas, Ehsan A. R.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Water use alternatives for Navajo energy production (open access)

Water use alternatives for Navajo energy production

The Navajo have substantial resources of coal and uranium, and water use is certain to accompany development of these resources. A variety of supplies, however, are available--water in storage in Navajo Reservoir, water in existing uses which may be transferred, and groundwater. Furthermore, the quantity of water use varies over a wide range depending on the use of water conservation technologies such as dry coolers and wastewater treatment units. Joint management of energy and water resources requires a basic understanding of the water supply and demand alternatives available to the energy industry. Thus, the uses of water for key energy activities--coal and uranium mining, coal transportation (slurry pipelines), and coal conversion (electricity and synthetic gas production) are reviewed. For those activities for which water conservation is feasible, the technologies and estimate costs ($/af saved) are described. The range of water requirements are then compared to energy and water resource estimates. Finally, alternative (not necessarily exclusive) criteria for energy and water resource management are discussed: a) promote energy activities with the lowest minimum water requirements; b) require industry to use low-quality water resources and the most effective water conservation technology; and c) maximize the economic return on Navajo water resources ($/af …
Date: January 1, 1979
Creator: Abbey, D.
Object Type: Article
System: The UNT Digital Library
Topics in the QCD phenomenology of deep-inelastic scattering. [Review] (open access)

Topics in the QCD phenomenology of deep-inelastic scattering. [Review]

The status of QCD with respect to recent results from deep-inelastic neutrino scattering is described emphasizing the theoretical uncertainties coming from effects of nonleading order in 1/Q/sup 2/ and in ..cap alpha../sub s/. 31 references.
Date: March 1, 1979
Creator: Abbott, L.F.
Object Type: Article
System: The UNT Digital Library
Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics (open access)

Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated.
Date: December 1, 1979
Creator: Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B0172.0014]

Photograph used for a story in the Oklahoma Times newspaper. Caption: "Brentwood Forest Apartments, 777 SE 15, was purchased this week by McCombs Properties II, Ltd., a California firm."
Date: August 13, 1979
Creator: Abbott, Signa
Object Type: Photograph
System: The Gateway to Oklahoma History
Large aperture contact ionized Cs/sup +1/ ion source for an induction linac (open access)

Large aperture contact ionized Cs/sup +1/ ion source for an induction linac

A 500 KeV one-ampere Cs/sup +1/ ion beam has been generated by contact ionization with a 30 cm dia. iridium hot plate. Reproducibility of space charge limited ion current wave forms at repetition rates up to 1 Hz has been verified. The beam is characterized to be very bright and suitable as an ion source for the induction linac based heavy ion fusion scheme. The hot anode plate was found to be reliable and self-cleaning during the operation.
Date: March 1979
Creator: Abbott, Steven; Chupp, Warren; Faltens, Andris; Herrmannsfeldt, William; Hoyer, Egon; Keefe, Denis et al.
Object Type: Article
System: The UNT Digital Library
QIKMIX: a quick-turnaround computer program for computing opacities of mixtures (open access)

QIKMIX: a quick-turnaround computer program for computing opacities of mixtures

QIKMIX is a quick-turnaround computer code developed to compute the radiative Rosseland mean opacity of specified mixtures at specified temperature and density points. The QIKLIB data base, which QIKMIX uses, has been derived from the OPLIB library. For most mixtures, QIKMIX can compute opacities over a temperature range of 50 to 25,000 eV in less than 1 min of CDC 7600 computer time. The purpose of this report is to discuss the QIKLIB data base and the operation of the QIKMIX code.
Date: May 1, 1979
Creator: Abdallah, J. Jr. & Huebner, W.F.
Object Type: Report
System: The UNT Digital Library
Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR] (open access)

Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR]

The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool so that its subsequent downward growth in the concrete may be slowed. In the second experiment a two-layer immiscible liquid system is volumetrically heated and allowed to melt into a low-density gas releasing solid bed which is miscible in the initially-higher-density bottom liquid. The solid melts, mixes with, and dilutes the bottom liquid pool until its density is lower than that of the top liquid.
Date: December 26, 1979
Creator: Abdel-Khalik, S I
Object Type: Report
System: The UNT Digital Library
Growth of molten core debris pools in concrete. Progress report, April 1--June 30, 1979. [LMFBR] (open access)

Growth of molten core debris pools in concrete. Progress report, April 1--June 30, 1979. [LMFBR]

The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool so that its subsequent downward growth in the concrete may be slowed. In the second experiment a two-layer immiscible liquid system is volumetrically heated and allowed to melt into a low-density gas-releasing solid bed which is miscible in the initially-higher-density bottom liquid. The solid melts, mixes with, and dilutes the bottom liquid pool until its density is lower than that of the top liquid. At this time pool inversion occurs and the immiscible liquid sinks to the bottom of the pool displacing the now lighter fuel-concrete simulant.
Date: July 1, 1979
Creator: Abdel-Khalik, S I
Object Type: Report
System: The UNT Digital Library
Results of Systems Studies for the STARFIRE Commercial Tokamak (open access)

Results of Systems Studies for the STARFIRE Commercial Tokamak

Extensive system and tradeoff studies were performed to support the selection process for the major parameters and design features of the STARFIRE commercial reactor. With a thermal power of 3800 MW, a neutron wall load of 3.5 MW/m/sup 2/ results in a relatively small-size reactor without imposing excessive requirements on the first-wall cooling capability, maximum toroidal-magnetic field, and frequency of structural material requirements. This moderately high-wall load requires that the first-wall coolant be liquid (water or lithium) and the lifetime of the structural material is > 15 MW-y/m/sup 2/. With moderate plasma elongation and beta the required maximum toroidal-field is approx. 11 T. STARFIRE is operated steady-state with no OH coil. The absence of an OH coil makes it possible to design the reactor with a low-aspect ratio (approx. 2.5) and small major radius. However, higher aspect ratios (approx. 3.5-4) are favored when the plasma current is driven with rf because the power required for the current drive, P/sub rf/, is much larger at lower aspect ratio. Since P/sub rf/ increases at lower plasma temperature, the optimum design for STARFIRE requires operation with plasma temperatures higher than those normally selected for designs with OH-driven current.
Date: January 1, 1979
Creator: Abdou, M. A.; Ehst, D. A. & Waganer, L. M.
Object Type: Article
System: The UNT Digital Library
Shielding and Maintainability in an Experimental Tokamak (open access)

Shielding and Maintainability in an Experimental Tokamak

This paper presents the results of an attempt to develop an understanding of the various factors involved. This work was performed as a part of the task assigned to one of the expert groups on the International Tokamak Reactor (INTOR). However, the results of this investigation are believed to be generally applicable to the broad class of the next generation of experimental tokamak facilities such as ETF. The shielding penalties for requiring personnel access are quantified. This is followed by a quantitative estimate of the benefits associated with personnel access. The penalties are compared to the benefits and conclusions and recommendations are developed on resolving the issue.
Date: January 1, 1979
Creator: Abdou, M. A.; Fuller, G.; Hager, E. R. & Vogelsang, W. F.
Object Type: Article
System: The UNT Digital Library
Influence of access hole parameters on neutron moisture probe readings (open access)

Influence of access hole parameters on neutron moisture probe readings

Computing soil moisture content with a neutron probe requires use of a calibration curve that considers the thermal neutron capture cross section of the hole liner, as well as the hole diameter. The influence of steel, polyvinyl chloride, and aluminum casings that fit 0.051- to 0.102-m hole diameters was determined by comparison with neutron probe readings in uncased holes of corresponding diameters. Eccentricity of probe location was considered a potentially significant variable. The experiment was run in disturbed Bandelier tuff with an average dry density of 1.35g . cm/sup -3/ and moisture content of 3.8 to 26.7% by volume. The casing material and hole diameter influenced the probe readings significantly, whereas eccentric location of the probe did not. Regression analyses showed an almost perfect inverse linear correlation between hole diameter and count rate.
Date: October 1, 1979
Creator: Abeele, W.V.
Object Type: Report
System: The UNT Digital Library
The Citizens Journal (Atlanta, Tex.), Ed. 1 Thursday, March 29, 1979 (open access)

The Citizens Journal (Atlanta, Tex.), Ed. 1 Thursday, March 29, 1979

Weekly newspaper from Atlanta, Texas that includes local, state and national news along with extensive advertising.
Date: March 29, 1979
Creator: Abeles, Neil
Object Type: Newspaper
System: The Portal to Texas History
Use of a General Nonlinear Least-Squares Curve Fitting Program With Nonclosed Form Relationships. [GNLS, in FORTRAN for CDC Computers] (open access)

Use of a General Nonlinear Least-Squares Curve Fitting Program With Nonclosed Form Relationships. [GNLS, in FORTRAN for CDC Computers]

A use for GNLS, a general nonlinear least-squares curve fitting program, is presented. In this use GNLS determines a set of best parameters for relationships that cannot be written in closed form. This program can be useful for experimenters who need to determine experimental parameters by fitting nonclosed-form relationships to experimental data. Two examples are given to indicate how GNLS can be used for this type of problem. 11 figures.
Date: December 26, 1979
Creator: Abey, A. E.
Object Type: Report
System: The UNT Digital Library
[Abilene City Council Minutes: 1979-1980] (open access)

[Abilene City Council Minutes: 1979-1980]

Ledger containing minutes of the City Council in Abilene, Texas documenting the group's discussions and activities from June 1979 through July 1980. A handwritten alphabetical index is at the start of the ledger.
Date: 1979-06-28/1980-07-24
Creator: Abilene (Tex.)
Object Type: Book
System: The Portal to Texas History
Abilene Fire Department Annual Report: 1979 (open access)

Abilene Fire Department Annual Report: 1979

Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1979.
Date: 1979
Creator: Abilene (Tex.). Fire Department.
Object Type: Report
System: The Portal to Texas History
[Program: The Music Man, 1979] (open access)

[Program: The Music Man, 1979]

Program for a production of The Music Man at Abilene Christian University performed at the Abilene Civic Center Theatre from October 25th to 28th, 1979. It includes a list of cast and staff, and other information about the play.
Date: 1979
Creator: Abilene Christian College
Object Type: Pamphlet
System: The Portal to Texas History