Partner
UNT Libraries Government Documents Department
4,941
UNT Libraries Special Collections
120
Oklahoma Historical Society
97
Rice University Woodson Research Center
17
Hoston History Research Center at Houston Public Library
13
Dublin Public Library
12
Sachse Public Library
11
Brownwood Public Library
10
Sterling Municipal Library
10
National WASP WWII Museum
8
89 More
Collection
Office of Scientific & Technical Information Technical Reports
4,912
Texas Digital Newspaper Program
241
KXAS-NBC 5 News Collection
109
Oklahoma Digital Newspaper Program
107
Tocker Foundation Grant
107
The Oklahoma City Times
18
Abilene Library Consortium
17
Texas Cultures Online
14
Altus Times-Democrat
13
John J. Herrera Papers
13
132 More
Country
States
Year
Month
Day
Language
5,435 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
5,435
next
Computer simulation of LMFBR piping systems. [Accident conditions]
Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Breeder Reactors (LMFBR). Hypothetical core disruptive accidents (HCDA) and water-sodium interaction are two examples of sources of high pressure pulses that endanger the integrity of the heat transport piping systems of LMFBRs. Although plastic wall deformation attenuates pressure peaks so that only pressures slightly higher than the pipe yield pressure propagate along the system, the interaction of these pulses with the different components of the system, such as elbows, valves, heat exchangers, etc.; and with one another produce a complex system of pressure pulses that cause more plastic deformation and perhaps damage to components. A generalized piping component and a tee branching model are described. An optional tube bundle and interior rigid wall simulation model makes such a generalized component model suited for modelling of valves, reducers, expansions, and heat exchangers. The generalized component and the tee branching junction models are combined with the pipe-elbow loop model so that a more general piping system can be analyzed both hydrodynamically and structurally under the effect of simultaneous pressure pulses.
Date:
January 1, 1977
Creator:
A-Moneim, M.T.; Chang, Y.W. & Fistedis, S.H.
Object Type:
Article
System:
The UNT Digital Library
Uranium hydrogeochemical and stream sediment reconnaissance in Lincoln and Flathead Counties, northwest Montana
Between mid-May and late June 1976, 3409 water and water-transported sediment samples were collected from 1781 locations spread over an approximate 17000-km/sup 2/ area of northwestern Montana. All of the samples were analyzed for total uranium at the LASL, using standardized procedures and rigorous quality controls, the waters by fluorometry and the sediment (and those waters with greater than 10 ppb uranium) by delayed-neutron counting methods. All of the field collection, treatment, and packaging of the samples was performed following strict LASL specifications. The uranium concentrations measured in the waters range from undetectable (less than 0.2) ppb to 173.6 ppb, but average only 0.66 ppb. The low uranium concentrations in the waters of this area are thought to be due primarily to a general lack of readily soluble uranium and dilution with spring runoff. Those locations which did have abnormally high uranium were examined more closely, and follow-up field examinations are recommended in the vicinity of some of these sites. The uranium content of the sediment samples range from 0.5 ppM to 52.2 ppM and average 4.56 ppM. Sample locations with high and/or anomalous uranium values were examined with respect to the local geology, water chemistry, and other relevant factors. …
Date:
May 1, 1977
Creator:
Aamodt, P. L.
Object Type:
Report
System:
The UNT Digital Library
Hydraulic fracture experiments in GT-1 and GT-2
Hydraulic fracturing experiments were conducted in granite rock, at temperatures near 100 and 150/sup 0/C, in two wells 0.785 km (2575 ft) and 1.98 km (6500 ft) deep near Los Alamos, New Mexico. No unusual difficulty was observed in fracturing crystalline rock hydraulically. The apparent surface energy (energy required to create new fracture surface by breaking the rock) was measured as 100 J/m/sup 2/. Orientation of the deeper fracture was measured as N35/sup 0/E (+-5/sup 0/). The fraction of fluid injected into the rock that could be recovered at hydrostatic surface pressure was measured. The efficiency of recovery was as high as 92 percent after the fracture impedance was lowered by ''propping'' the fracture with sand. Permeability of the rock over the face of the fracture was compatible with laboratory measurements (10/sup -7/ to 10/sup -8/ darcys). Downhole pressures required to extend the fractures were about 150 and 340 bars (2175 and 4900 psi), respectively.
Date:
February 1, 1977
Creator:
Aamodt, R. L.
Object Type:
Report
System:
The UNT Digital Library
BNL Archive and Dissemination System. [For accessing data files constructed at separate places and times]
The Brookhaven National Laboratory Archive and Dissemination System (BNLADS) is designed to deal with the record keeping associated with archiving and disseminating sequential files through a computer network. This data base management system (DBMS) is implemented in a host language that is a subset of PL/I. The stored sequential files that can be dealt with by the BNLADS must be in character mode (ASCII, BCD, EBCDIC). The accessing of fields is specified by a format description which allows for forward processing of fields only. The structure of a case type statement allows for a data field determining a format sequence from a set of format sequences. A data description language (DDL) was devised to describe the accessing sequence of stored sequential files. A data model definition gives the user a view of the content of each stored sequential file. The DDL requires all field type references to contain the field name, so that the BNLADS can access all stored sequential files by logical field name and can write stored sequential files by stating the logical field name without the necessity of referring to formats. The BNLADS is architected in a stratified form in which the application programs are built on …
Date:
February 1, 1977
Creator:
Abbey, S; Fuchel, K; Heller, J; Lin, K S & Osterer, L
Object Type:
Article
System:
The UNT Digital Library
Growth of molten core debris pools in concrete. Progress report, March 1, 1977--November 30, 1977. [LMFBR]
Experiments have been conducted using a volumetrically-heated pool with noncondensable gas injection at the boundaries to simulate the heat transfer processes taking place in molten core debris/concrete systems. Measurements of the upward, downward, and sideward heat transfer rates have been made over wide ranges of internal Rayleigh number (6.0 x 10/sup 5/ < Ra < 2.7 x 10/sup 9/), superficial gas velocity (0 < V/sub g/ < 2.5 cm/min), and pool aspect ratio (1.32 < W/L < 5.16). Pools with either an isothermal solid upper boundary or a free surface have been examined. Detailed measurements of the temperature distribution within the pools have also been made. The results indicate that the downward heat transfer rates are significantly increased while the sideward heat transfer rates are slightly affected by gas injection. The heat transfer rates at the pool boundaries are sensitive to the upper surface boundary condition. Efforts are continuing on the second part of the present study where the phase-change and gas evolution processes are combined.
Date:
November 1, 1977
Creator:
Abdel-Khalik, S I
Object Type:
Report
System:
The UNT Digital Library
Radiation considerations for superconducting fusion magnets
Radiation environment for the magnets is characterized for various conditions expected for tokamak power reactor operation. The radiation levels are translated into radiation effects using available experimental data. The impact of the tradeoffs in radiation shielding and the change in the properties of the superconducting magnets on reactor performance and economics is examined. It is shown that (1) superconducting magnets in fusion reactors will operate at much higher radiation level than was previously anticipated; (2) additional data on radiation damage is required to better accuracy than is presently available in order to accurately quantify the change in properties in the superconducting magnet components; and (3) there is a substantial penalty for increasing (or overestimating) the shielding requirements. A perspective of future tokamak power reactors is presented and questions relating to desirable magnetic field strength and selection of materials for superconducting magnets are briefly examined.
Date:
January 1, 1977
Creator:
Abdou, M. A.
Object Type:
Article
System:
The UNT Digital Library
Impact of Major Design Parameters on the Economics of Tokamak Power Plants
A parametric systems studies program is now in an active stage at Argonne National Laboratory. This paper presents a summary of results from this systems analysis effort. The impact of major design parameters on the economics of tokamak power plants is examined. The major parameters considered are: (1) the plant power rating; (2) toroidal-field strength; (3) plasma ..beta../sub t/; (4) aspect ratio; (5) plasma elongation; (6) inner blanket/shield thickness; and (7) neutron wall load. The performance characteristics and economics of tokamak power plants are also compared for two structural materials (stainless steel and a vanadium alloy).
Date:
November 1, 1977
Creator:
Abdou, M. A.; Ehst, D.; Maroni, V. & Stacey, W. M. Jr.
Object Type:
Article
System:
The UNT Digital Library
Speciation studies of radionuclides in low level wastes and process waters from pressurized water reactor
Physicochemical characterization studies of aqueous process streams at San Onofre Generating Station Unit No. 1 are providing important source term information concerning the forms of radionuclides being released into the marine environment. The primary coolant, secondary steam condensate, processed low level wastes and tertiary coolant were sampled at several different times in the nuclear fuel cycle. Rdionuclides were partitioned into particulate, cationic, anionic, and nonionic species in the reactor process streams, and into particulate and soluble species in the tertiary seawater coolant. Characterization of the particulate species has included a detailed size distribution. The purpose of this research was to provide information concerning chemical and physical forms of the radionuclides being released to the coastal zone from a nuclear generating station in order to facilitate design of radiobiological studies necessary for assessment of their environmental significance.
Date:
October 1, 1977
Creator:
Abel, K. H.; Robertson, D. E.; Crecelius, E. A. & Silker, W. B.
Object Type:
Article
System:
The UNT Digital Library
Energy modeling and data support for the Electric Power Research Institute. Annual report, July 1977
Progress for the period from July 1, 1976 to June 30, 1977 is reviewed in this second annual report in support of the Energy Modeling and Data Support program for EPRI. Reference Energy Systems were formulated for the base year 1972 and projections developed for the years 1980, 1985, and 2000 for the area serviced by the New York Power Pool. In addition, Brookhaven, EPRI, and the Tennessee Valley Authority have entered into a cooperative effort to develop demand projections for the area serviced by TVA. The RES and associated data will provide a baseline against which TVA can evaluate the effect of substituting alternate technologies and policies for one another. Development of the Dynamic Energy Systems Optimization Model is continuing, with effort this year directed toward better representation of the electrical sector within the model. The model has been reformulated such that the year is divided into three seasons and two daily divisions, thus allowing the model to choose whether a summer or winter peak will occur and better depict the yearly time dependence of demands.
Date:
July 1, 1977
Creator:
Abilock, H.; Beller, M.; Cherniavsky, E. A.; Hermelee, A.; Juang, L. L. & Marcuse, W.
Object Type:
Report
System:
The UNT Digital Library
Neutron-induced mutation experiments. Progress report, March 1, 1977--February 28, 1978. [Drosophila female gonial cell exposure]
Experiments have been carried out to study the relative mutagenic effectiveness for Drosophila female germ cells of neutrons of different energies employing X-linked recessive lethal and specific locus mutation tests. The energies and doses employed to date to study X-linked lethals are 0.43 MeV (500, 1000, 1500, 1900 R (in progress)), 0.68 MeV (250, 500, 1000, 1500 R), 2 MeV (250, 500, 1000, 1500, 2000 R), 6 MeV (250, 500, 1500, 3000 R) and 15 MeV (250, 500, 1000, 1500, 3000 R). 0.43-MeV neutrons appear to have an RBE in the range 1.9 to 4.7, 0.68 MeV 2.8 to 4.3, 2 MeV (incomplete data), 6 MeV 1.7 to 3.2, and 15 MeV 1.7 to 2.2. The data for 0.43-MeV and 0.68-MeV neutrons do not yet differentiate between a linear and a quadratic dose/frequency response curve for the doses studied, but suggest a quadratic relationship. The data for 2, 6 and 15 MeV are inconclusive. The specific locus mutation data indicate the highest RBE for 0.68-MeV neutrons, followed by 2 and 6 MeV, respectively.
Date:
November 1, 1977
Creator:
Abrahamson, S.
Object Type:
Report
System:
The UNT Digital Library
Genetic effects of low x-ray doses. Progress report, October 1, 1976--September 30, 1977. [In Drosophila]
A linear-quadratic model of dose-kinetics is proposed for x-ray induced recessive lethal mutations in oogonia of Drosophila. From this it should follow that at higher total doses fractionation treatments should give a lower yield of mutations than an equivalent acute exposure. A dose of 6000 R, given acutely and in 3 different fractionation regimes gave results in the expected direction for 2 x 3000 R, and a significant decrease for 3 x 2000 R and for 4 x 1500 R fractionations.
Date:
September 1, 1977
Creator:
Abrahamson, S. & Meyer, H.U.
Object Type:
Report
System:
The UNT Digital Library
As low as is reasonably achievable (ALARA) studies relative to the NWTS program
The history of development of the as-low-as-is-reasonably achievable (ALARA) concept and ALARA criteria for radiation exposures as applied to both off-site (environmental) and on-site (occupational) exposures at nuclear power plants are reviewed. The current status of activities within the various federal agencies directed toward developing ALARA criteria for other areas of the nuclear fuel cycle is presented. Based on the historical development, the present activities, and on discussions with numerous people involved in this area, the future development of ALARA criteria and implications for the National Waste Terminal Storage (NWTS) Program is forecast. Environmental ALARA criteria which relate to minimizing radiation to the surrounding populaltion are discussed along with current occupational ALARA criteria and quidelines for risk-benefit assessments that are under development and recommendations to assure that evolving ALARA concepts are periodically brought up to date and that such concepts be made available to those subcontractors who have responsibility for design and operation of a repository. An annotated bibliography of some 83 sources giving information on ALARA criteria and its application is included. (JRD)
Date:
October 1, 1977
Creator:
Abrams, L. A.; Schlegel, R. L. & Sullivan, R. P.
Object Type:
Report
System:
The UNT Digital Library
[Letter from Volney A. Acheson to Mr. and Mrs. Avery McClurg, July 1, 1977]
Letter from Volney A. Acheson to Mr. and Mrs. Avery McClurg discussing the attached photocopies of documents related to the life and work of T. V. Munson. The attached papers include a list of mentions of Munson family members in the Denison Gazetteer, and photographs of the Vinita House and T. V. Munson's awards.
Date:
July 1, 1977
Creator:
Acheson, Volney A.
Object Type:
Letter
System:
The Portal to Texas History
Advanced fuel cell development progress report, April--June 1977. [Electrolyte mixtures of Li/sub 2/CO/sub 3/-K/sub 2/CO/sub 3/ containing rod-shaped particles of. beta. -LiAlO/sub 2/]
This report describes advanced fuel cell research and development activities at Argonne National Laboratory (ANL) during the period April--June 1977. These efforts have been directed toward understanding and improvement of molten-carbonate-electrolyte fuel cells operating at temperatures near 923 K. A primary focus of the work has been on developing electrolyte structures which have high strength and conductivity, as well as good electrolyte retention, and on developing methods of synthesis for electrolyte structures that are amenable to mass production. A low temperature synthesis which produces material having rodlike particles of ..beta..--LiAlO/sub 2/ has been refined and is now used for preparing electrolytes. Cell testing is essential for understanding and evaluating individual component behavior and the interactions of the components under realistic operating conditions. Most of the testing to date has been conducted in a 7-cm (2/sup 3///sub 4/-in.)-dia cylindrical cell with Type 316 stainless steel housings and current collectors, a nickel anode, and a nickel oxide cathode. Testing has begun to probe the roles of anode, cathode, and electrolyte in cell performance, and has provided verification of an acceptable technique for prevention of seal corrosion for at least 1400 hours. Components evaluation and development include post-test analysis and evaluation of cell …
Date:
August 1, 1977
Creator:
Ackerman, J P; Kinoshita, K; Sim, J W; Swaroop, R & Nelson, P A
Object Type:
Report
System:
The UNT Digital Library
Advanced fuel cell development. Progress report for January--March 1977.
Advanced fuel cell research and development activities at Argonne National Laboratory (ANL) during the period January to March 1977 is described. Efforts have been directed toward understanding and improvement of molten carbonate electrolyte fuel cells operating at temperatures near 650/sup 0/C. A primary focus of the work has been on developing electrolyte structures which have high strength and conductivity, as well as good electrolyte retention, and on developing methods of synthesis for electrolyte structures that are amenable to mass production. Several synthesis methods have been investigated, and at least one appears to yield a highly desirable product and to greatly simplify production. Cell testing is essential for understanding and evaluating individual component behavior and the interactions of the components under realistic operating conditions. Most of the testing to date has been conducted in a 2/sup 3///sub 4/-in.-dia cylindrical cell with Type 316 stainless steel housings and current collectors, a nickel anode, and a nickel oxide cathode. Reproducible cell operation has been achieved in these cells, and operational parameters have been brought under control. Necessary improvements in cell components have been defined, and a systematic program of optimization has begun. Components evaluation and development include post-test analysis and evaluation of all …
Date:
June 1, 1977
Creator:
Ackerman, J P; Kinoshita, K; Sim, J W; Swaroop, R & Nelson, P A
Object Type:
Report
System:
The UNT Digital Library
Comparison of the thermodynamic properties and high temperature chemical behavior of lanthanide and actinide oxides
The thermodynamic properties of the lanthanide and actinide oxides are examined, compared, and associated with a variety of high temperature chemical behavior. Trends are cited resulting from a number of thermodynamic and spectroscopic correlations involving solid phases, species in aqueous solution, and molecules and ions in the vapor phase. Inadequacies in the data and alternative approaches are discussed. The characterization of nonstoichiometric phases stable only at high temperatures is related to a network of heterogeneous and homogeneous equilibria. A broad perspective of similarity and dissimilarity between the lanthanides and actinides emerges and forms the basis of the projected needs for further study.
Date:
January 1, 1977
Creator:
Ackermann, R. J. & Rauh, E. G.
Object Type:
Article
System:
The UNT Digital Library
Thermal conductivity of S. E. New Mexico rocksalt and anhydrite. [Saltcrete]
The thermal conductivity of several rocksalt materials has been determined. Some of the materials were core samples from well AEC 8, Carlsbad, New Mexico. These samples ranged from nearly pure halite (NaCl) to nearly pure anhydrite (CaSO/sub 4/). Core sample crystallite size ranged from about 3 centimeters to essentially packed salt sand (approx. = 0.5mm). The samples exhibited thermal conductivities from approx. = 1.5 to 7.5 W/mK which depended upon purity and grain size. A one meter cube of rocksalt from the Mississippi Chemical Company's S.E. New Mexico potash mine was obtained for other experiments. The thermal conductivity of one sample from each of the orthogonal directions of the cube was measured. This material had a high conductivity of approx. = 8.5 W/mK and was very isotrophic. A core of rocksalt from the Morton Salt Company, Paynesville, Ohio had a thermal conductivity of 6 W/mK, which is in the upper band of the results on cores from well AEC 8. Finally, a concrete made with salt sand and rocksalt aggregate was determined to have a conductivity of approx. = 2 W/mK. A longitudinal heat flow apparatus was used to determine the thermal conductivity. An analysis of the experiment gave an …
Date:
January 1, 1977
Creator:
Acton, R.U.
Object Type:
Article
System:
The UNT Digital Library
Dosimeter sample preparation, quality assurance, and materials development for the ILRR, FRMDC, and FFTF dosimetry programs
Since the IRML dosimeter program began in 1971, approximately 1900 vanadium encapsulated dosimeters and approximately 100 aluminum encapsulated metal fission foils have been prepared to meet TLRR, FRMDC, and FFTF requirements. Development efforts have focused on cost reduction in fabrication as well as characterization of both pure and dilute materials to meet the desired accuracy goals of +-0.5 and +-1.0 percent (2 sigma), respectively. One important requirement of the dosimeter program is that the dosimeter materials be encapsulated in high purity vanadium. To meet this requirement over the next ten years, an adequate supply of vanadium must be maintained. Efforts were begun to locate and characterize batches of high purity vanadium to meet this requirement. In addition, efforts were initiated to obtain the necssary vanadium capsules, to be fabricated from ILRR material, on a competitive bid basis from a commercial supplier. Quality assurance procedures were established to maintain homogeneity among the various batches of dosimeters produced. Procedures developed for producing the 1.270-mm diameter capsules were adapted to the loading of the more recently required 0.889-mm diameter capsules. Vanadium capsules are to be used in neutron energy spectra, flux and fluence characterization studies during start-up and run phases of the FFTF.
Date:
January 1, 1977
Creator:
Adair, H. L.; Kobisk, E. H.; Setaro, J. A.; Quinby, T. C. & Dailey, J. M.
Object Type:
Article
System:
The UNT Digital Library
Preparation and characterization of /sup 241/Am and /sup 3/H targets
This paper describes actinide oxide deposits in support of reactor technology, high purity /sup 241/Am metal fabrication for material property studies and tritium target fabrication in support of materials research conducted at LLL.
Date:
January 1, 1977
Creator:
Adair, H.L.
Object Type:
Article
System:
The UNT Digital Library
Current trends in methods for neutron diffusion calculations
Current work and trends in the application of neutron diffusion theory to reactor design and analysis are reviewed. Specific topics covered include finite-difference methods, synthesis methods, nodal calculations, finite-elements and perturbation theory.
Date:
January 1, 1977
Creator:
Adams, C. H.
Object Type:
Article
System:
The UNT Digital Library
Radiation hardened field oxide
This paper describes the development of a radiation-tolerant field oxide compatible with both MOS and bipolar technologies. Data is presented which illustrates that nonguardbanded devices utilizing conventional field oxide structures cannot be expected to survive an ionizing radiation dose above approximately 5 x 10/sup 4/ rads (Si) due to inversion of p-type silicon surfaces under metallized areas. The radiation hardened oxide was evaluated with both aluminum and polycrystalline silicon gate MOS structures and they conclusively demonstrate that this oxide eliminates the field inversion problem for radiation levels in excess of 10/sup 6/ rads (Si).
Date:
January 1, 1977
Creator:
Adams, J. R.; Dawes, W. R. & Sanders, T. J.
Object Type:
Article
System:
The UNT Digital Library
Considerations in the evaluation of the human element of a safeguards system
By understanding the human system and its function, then a structure for evaluating the human system can be developed. This understanding must be available at the research and development levels, and must occur at the working level so that individuals who impact the system will have a common goal in mind. Then by appropriate coordination and review, a system can be developed which will function as designed with a high degree of assurance.
Date:
January 1, 1977
Creator:
Adams, K.G. & Trujillo, A.A.
Object Type:
Article
System:
The UNT Digital Library
Material control assessment procedure
The material control system assessment procedure being developed by the Lawrence Livermore Laboratory for the U.S. Nuclear Regulatory Commission is reviewed. It consists of five major sections: Target Identification, Adversary Sequence and Simuli Generation, Material Control System Response Determination, Safeguard System Outcome Determination, and Safeguard System Utility Determination. When adopted, this procedure will reduce safeguards licensing problems by providing compatibility with future performance based regulations, explicit evaluation rules and requirements, well-defined trade-off structures, and user-oriented and systematic evaluation and design tools.
Date:
June 1, 1977
Creator:
Adams, R. W. & Spogen, L. R.
Object Type:
Article
System:
The UNT Digital Library
Material control assessment procedure
The material control system assessment procedure being developed by the Lawrence Livermore Laboratory for the U.S. Nuclear Regulatory Commission is reviewed. It consists of five major sections: Target Identification, Adversary Sequence and Simuli Generation, Material Control System Response Determination, Safeguard System Outcome Determination, and Safequard System Utility Determination. When adopted, this procedure will minimize safeguards licensing problems by providing compatibility with future performance based regulations, explicit evaluation rules and requirements, well-defined trade-off structures, and user-oriented and systematic evaluation and design tools.
Date:
June 1, 1977
Creator:
Adams, R. W. & Spogen, L. R.
Object Type:
Article
System:
The UNT Digital Library