U N T Established 1890 U N T
University Libraries

Digital Collections

Access

Resource Type

Partner

Collection

Serial/Series Title

Degree Department

Degree Discipline

Degree Level

Country

States

Counties

Decade

Year

Month

Day

Language

85,776 Matching Results

Start Over Day 30th

Results open in a new window/tab.

prev Results: 25 - 48 of 85,776 next
Best Match Title Creator Date Created (Newest) Date Created (Oldest) Date Added (Newest) Date Added (Oldest)
Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1 (open access)

Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1

A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with a total activity of 1200 mu c. A quantity of 6,670 gal. of reactor coolant effluent was processed. Approximately 634 lb of combustible waste were incinerated. (M.C.G.)
Date: June 30, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962 (open access)

Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME II. PLANT DRAWINGS (open access)

PL FINAL DESIGN REPORT. VOLUME II. PLANT DRAWINGS

Plant drawings for the final design for the Army Reactor (PL-2) are presented. Two hundred and twenty-eight figures are included. (M.C.G.)
Date: June 30, 1961
Creator: Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
Object Type: Report
System: The UNT Digital Library
Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator (open access)

Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator

Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, and bayonet tube weld cap test are discussed. (M.C.G.)
Date: October 30, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Preliminary evaluation of two-element optical concentrators for use in solar photovoltaic systems (open access)

Preliminary evaluation of two-element optical concentrators for use in solar photovoltaic systems

The objective of this program was: to evaluate for photovoltaic applications the use of the compound parabolic concentrator design as a field collector--in conjunction with a primary focusing concentrator. The primary focusing concentrator may be a parabolic reflector, an array of Fresnel mirrors, a Fresnel lens, or some other type; Select several candidate configurations of such compound systems (focusing concentrators/CPC field collectors); Perform an analytic evaluation of the technical performance of these systems; and identify the most promising configurations and perform a cost effectiveness study pertinent to coupling CPC concentrators to solar cells. (WDM)
Date: June 30, 1975
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Characterization of carbonaceous materials using extraction with supercritical pentane (open access)

Characterization of carbonaceous materials using extraction with supercritical pentane

The use of carbonaceous adsorbents is limited by irreversible adsorption of some compounds so the use of supercritical pentane as an extracting solvent was examined. Carbon black appeared to be broken down slowly, but continuously, by the penane. To see if other types of carbon behaved similarly, high purity graphite, technical grade graphites, active carbons, and charcoals were examined. The extracts were characterized by uv spectroscopy, packed column chromatography using flame ionization and flame photometric detectors, and capillary GC/MS. The extracts were characteristic for each class of carbonaceous material. The high purity graphite yielded large, polycyclic aromatic compounds; the technical grade graphites yielded alkanes and alkyl-substituted benzenes and naphthalenes; the active carbons yielded alkanes, dienes, and small amounts of alkyl-substituted benzenes; and the charcoals yielded almost entirely alkanes in small amounts.
Date: May 30, 1980
Creator: Fetzer, J.C.; Graham, J.A.; Arrendale, R.R.; Klee, M.S. & Rogers, L.B.
Object Type: Report
System: The UNT Digital Library
Ocean thermal energy. Quarterly report, April-June 1982 (open access)

Ocean thermal energy. Quarterly report, April-June 1982

This quarterly report includes summaries of the following tasks: (1) OTEC pilot plant conceptual design review; (2) OTEC methanol; (3) management decision requirements for OTEC construction; (4) hybrid geothermal - OTEC (GEOTEC) power plant performance estimates; and (5) supervision of testing of pneumatic wave energy conversion system.
Date: June 30, 1982
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Free-electron laser generation of VUV and x-ray radiation using a conditioned beam and ion-channel focusing (open access)

Free-electron laser generation of VUV and x-ray radiation using a conditioned beam and ion-channel focusing

The use of ion-focusing and a conditioned beam greatly enhances FEL gain in the VUV and Soft X-Ray range. The equations governing FEL amplification are derived and results of a linear analysis are noted. Numerical results, including 3D effects and having an order of magnitude improvement in gain, are presented for a 30 {Angstrom} example. 3 refs., 2 figs., 1 tab.
Date: August 30, 1991
Creator: Yu, Li-Hua (Brookhaven National Lab., Upton, NY (United States)); Sessler, A. & Whittum, D.H. (Lawrence Berkeley Lab., CA (United States))
Object Type: Article
System: The UNT Digital Library
Model validation and sensitivity analysis of solar collector loops. Final technical report (open access)

Model validation and sensitivity analysis of solar collector loops. Final technical report

The experimental solar collector systems at Middlebury College have been modified to permit short time resolution studies of solar collector loop performance. A variety of experiments have been performed to measure the following system properties: (a) collector efficiency, (b) collector response to step changes in insolation, (c) collector response to the introduction of cold inlet water, and (d) pump cycling as a function of control sensor location and set points. Data from these experiments have been supplied to the solar group at Drexel for validation of their analytical collector loop model.
Date: July 30, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report (open access)

REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Object Type: Report
System: The UNT Digital Library
Resource Conservation and Recovery Act (RCRA) (open access)

Resource Conservation and Recovery Act (RCRA)

This Resource Conservation and Recovery Act (RCRA) Facility Investigation Program Plan has been developed to provide a framework for the completion of RCRA Facility Investigations (RFI) at identified units on the Savannah Rive Site (SRS) facility. As such, the RFI Program Plan provides: technical guidance for all work to be performed, managerial control, a practical, scientific approach. The purpose of this Overview is to demonstrate how the basic RFI Program Plan elements (technical, management, and approach) are interwoven to provide a practical and workable plan. The goal of the RFI Program Plan is to provide a systematic, uniform approach for performance and reporting. In addition, the RFI Program Plan has been developed to be specific to the SRS facility and to adhere to the Environmental Protection Agency (EPA) RFI guidance received as part of the SRS. The US EPA publication Characterization of Hazardous Waste Sites'' has been liberally adapted for use in this RFI Program Plan.
Date: June 30, 1989
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Chemistry research and development. Progress report, December 1978-May 1979. [Component, pilot plant, instrumentation] (open access)

Chemistry research and development. Progress report, December 1978-May 1979. [Component, pilot plant, instrumentation]

Progress and activities are reported on component development, pilot plant development, and instrumentation and statistical systems. Specific items studied include processing of pond sludge, transport of radioactive materials and wastes, corrosion, decontamination and cleaning, fluidized-bed incineration, Pu contamination of soils, chemical analysis, radiometric analysis, security. (DLC)
Date: June 30, 1980
Creator: Miner, F. J.
Object Type: Report
System: The UNT Digital Library
D7H-test results (open access)

D7H-test results

Data were reduced from the voltage-time relations stored in files D7H001 to D7H090 on HP1000. The I-B calibration curve is included. The data base is shown and can be used by the 9845B. The data include the quench location, Q/sub 2/ layer 1 top, Q/sub 3/ layer 1 bottom and the quench current and its normalized value with respect to short sample, I/sub c/ = 4920A at 4.4 K, I/sub c/ = 6710 A at 1.8 K. The resistance (..cap omega../cm) was calculated using the propagation time according to the voltage change across the measured sections. The conductor potential length are L/sub 5/ /sub 9/ = 48.6 cm, L/sub 6/ /sub 10/ = 17.9 cm, L/sub 7/ /sub 11/ = 40.6 cm. The turn to turn velocity V/sub t/ was calculated dividing the nominal turn to turn distance (58 mil) by the propagation time (Trans. Time). The quench time T/sub q/ was measured from the time the resistive rise starts until the energy extraction system fires.
Date: July 30, 1982
Creator: Caspi, S.
Object Type: Report
System: The UNT Digital Library
FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report (open access)

FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report

>The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces and where a larger thickness-todiameter ratio could be used than if the coating were on the surface of the graphite sphere. Fuel elements were irradiated to burnups ranging up to about 6 at.% U/sup 235/. In all specimens containing a uniform dispersion of fuel, the graphite spheres were found to retain their structural properties after irradiation. Data are given on fuel particle coatings of A1/sub 2/O/sub 3/, pyrolytic carbon, and metals: surface coatings of siliconized silicon carbide, pyrolytic carbon, and metal carbides; properties of and the effects of irradiation on graphite spheres; the use of natural graphite in preparing a high-density matrix material; graphite fueling by thorium nitrate infiltration; subsurface metal and metal carbide coatings for graphite; and an in-pile loop program on the behavior …
Date: April 30, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Double-mode pulsation (open access)

Double-mode pulsation

Double mode pulsation is a very pervasive phenomenon in stars all over the Hertzsprung-Russell diagram. In order of increasing radius, examples are: ZZ Ceti stars, the sun, the delta Scuti stars, RR Lyrae variables, the ..beta.. Cephei variables and those related to them, Cepheids, and maybe even the Mira stars. These many modes have been interpreted as both radial and nonradial modes, but in many cases the actual mode has not been clearly identified. Yellow giants seem to be the most simple pulsators with a large majority of the RR Lyrae variables and Cepheids showing only one pulsation period. We limit this review to those very few cases for classical Cepheids and RR Lyrae variables which display two modes. For these we know many facts about these stars, but the actual cause of the pulsation in two modes simultaneously remains unknown.
Date: July 30, 1982
Creator: Cox, A. N.
Object Type: Article
System: The UNT Digital Library
Engineering design solutions of flux swing with structural requirements for ohmic heating solenoids (open access)

Engineering design solutions of flux swing with structural requirements for ohmic heating solenoids

Here a more detailed publication is summarized which presents analytical methods with solutions that describe the structural behavior of ohmic heating solenoids to achieve a better understanding of the relationships between the functional variables that can provide the basis for recommended design improvements. The solutions relate the requirements imposed by structural integrity to the need for producing sufficient flux swing to initiate a plasma current in the tokamak fusion machine. A method is provided to perform a detailed structural analysis of every conducting turn in the radial build of the solenoid, and computer programmed listings for the closed form solutions are made available as part of the reference document. Distinction is made in deriving separate models for the regions of the solenoid where turn-to-turn radial contact is maintained with radial compression or with a bond in the presence of radial tension, and also where there is turn-to-turn radial separation due to the absence or the loss of bonding in the presence of would be radial tension. The derivations follow the theory of elasticity for a body possessing cylindrical anisotropy where the material properties are different in the radial and tangential directions. The formulations are made practical by presenting the methods …
Date: September 30, 1977
Creator: Smith, R. A.
Object Type: Article
System: The UNT Digital Library
PROGRAM ODD--A ONE-DIMENSIONAL MULTIGROUP CODE FOR THE IBM-7090 (ANP PROGRAM NO. 657) (open access)

PROGRAM ODD--A ONE-DIMENSIONAL MULTIGROUP CODE FOR THE IBM-7090 (ANP PROGRAM NO. 657)

The physical and mathematical reactor models which are used in Program ODD are discussed. In addition, the FORTRAN II source program listings, decimal data input sheets, and input and output for a sample case are given. Program ODD was designed to raake use of the Revised Nuclear Data System at ANPD which consists of twenty-five energy group cross-section data including high energy inelastic scattering matrices, resonance parameters for the resolved resonances, and thermalization scattering matrices for the near thermal energy region. The most unique aspect of the program is the mathematical technique employed for eliminating inner iterations and slow convergenc rates occasioned by the up- scattering'' in the thermalization region of the energy lattice. Direct inversion of the energy matrix coupling the thermal and last four epitherma groups provides simultaneous consistent solutions for thes groups within each power iteration. (auth)
Date: June 30, 1961
Creator: Fischer, P.G.; Wenstrup, F.D. & Hoffman, T.A.
Object Type: Report
System: The UNT Digital Library
State energy price and expenditure report 1989 (open access)

State energy price and expenditure report 1989

The State Energy Price and Expenditure Report (SEPER) presents energy price and expenditure estimates for the 50 States, the District of Columbia, and the United States. The estimates are provided by energy source (e.g., petroleum, natural gas, coal, and electricity) and by major consuming or economic sector. This report is an update of the State Energy Price and Expenditure Report 1988 published in September 1990. Changes from the last report are summarized in a section of the documentation. Energy price and expenditure estimates are published for the years 1970, 1975, 1980, and 1985 through 1989. Documentation follows the tables and describes how the price estimates are developed, including sources of data, methods of estimation, and conversion factors applied. Consumption estimates used to calculate expenditures, and the documentation for those estimates, are from the State Energy Data Report, Consumption Estimates, 1960--1989 (SEDR), published in May 1991. Expenditures are calculated by multiplying the price estimates by the consumption estimates, adjusted to remove process fuel and intermediate product consumption. All expenditures are consumer expenditures, that is, they represent estimates of money directly spent by consumers to purchase energy, generally including taxes. 11 figs., 43 tabs.
Date: September 30, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Determination of performance criteria for high-level solidified nuclear waste from the commercial nuclear fuel cycle: a probabilistic safety analysis (open access)

Determination of performance criteria for high-level solidified nuclear waste from the commercial nuclear fuel cycle: a probabilistic safety analysis

To minimize the radiological risk from the operation of a waste management system for the safe disposal of high-level waste, performance characteristics of the solidified waste form must be specified. The minimum waste form characteristics that must be specified are the radionuclide volatilization fraction, airborne particulate dispersion fraction, and the aqueous dissolution characteristics. The results indicate that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. The actual values of expected risk are sensitive to modeling assumptions and data base uncertainties. The transportation step appears to be the most limiting in determining the required performance characteristics.
Date: March 30, 1978
Creator: Heckman, R.A.
Object Type: Article
System: The UNT Digital Library
Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs (open access)

Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs

A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)
Date: January 30, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
CSU solar house I solar collector (open access)

CSU solar house I solar collector

None
Date: June 30, 1975
Creator: Ward, D.S.
Object Type: Article
System: The UNT Digital Library
Coal-oil mixture combustion program: injection into a blast furnace (open access)

Coal-oil mixture combustion program: injection into a blast furnace

A chemically stabilized coal-oil mixture (COM) was made and used as an auxiliary fuel in a blast furnace for 44 days. Approximately 485,000 gallons of COM were produced at an on-site COM plant. Composition was 47.9% coal, 47.6% No. 6 oil, 4.0% water, and 0.5% emulsifier. Average injection rates were 3.8 to 13.0 gpm during different periods of the trial. Coal handling equipment, mixing and processing equipment, pumps, piping, fuel lances, and instrumentation are discussed. The blast furnace performance during the trial is compared to a Base Period of injecting No. 6 oil. Blast furnace performance was satisfactory, with one pound of COM replacing one pound of coke or 0.8 pound of No. 6 oil. The production of COM and its usage in a blast furnace is economical and feasible.
Date: April 30, 1982
Creator: Jansto, S. G.; Mertdogan, A.; Marlin, L. A. & Beaucaire, V. D.
Object Type: Report
System: The UNT Digital Library
Thermal design and analysis of superconductors for the toroidal field coils of TNS. [NbTi] (open access)

Thermal design and analysis of superconductors for the toroidal field coils of TNS. [NbTi]

The toroidal field coils in two of the four TNS field coil design options are superconducting. NbTi superconductors are used in the low field design option and Nb/sub 3/Sn superconductors are used in the high field design option. The preliminary conceptual design parameters of the coils and the superconductors have been developed. The selected coil shape is the pure tension D-configuration. The superconductors are the multifilamentary, cabled design and are cooled by forced flow supercritical helium. Thermal stability analyses were performed for the superconductors. The cryogenic recovery capability of the NbTi superconductors is more than 10/sup 5/ J/m/sup 3/ of conductor plus helium volume and that of the Nb/sub 3/Sn is more than 3 x 10/sup 5/ j/m/sup 3/.
Date: September 30, 1977
Creator: Lee, A. Y.
Object Type: Article
System: The UNT Digital Library
Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum (open access)

Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum

Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.
Date: May 30, 1980
Creator: Kier, R.S.; Showalter, P.A. & Dettinger, M.D.
Object Type: Report
System: The UNT Digital Library