Degree Department

5,590 Matching Results

Results open in a new window/tab.

Effects of irradiation on ceramics for fusion-reactor applications (open access)

Effects of irradiation on ceramics for fusion-reactor applications

The purpose of this study, coordinated with efforts of LANL and Grumman Aircraft, was to lay some basic groundwork to study the irradiation effects on the engineering properties of some useful classes of ceramic materials; ANL's efforts were pointed towards multiphase materials (glass ceramics and partially-stabilized zirconias). The materials were irradiated at 400 and 550/sup 0/C to fast (E > 0.1 MeV) neutron fluences of approx. 2 x 10/sup 22/n/cm/sup 2/. Fluorophlogapite mica based glass ceramics (Macor, etc.) were found susceptible to weakening due to void formtion between mica plates. Composition variations within this class of glass ceramics seemed to cause sharp variations in the magnitude of the effect. Lithium silicate glass ceramic (ReX) showed sharp contrasts between the effects of ionization irradiation and displacement damage, neutron irradiation having little effect on the ReX structure while electron irradiation creating lithium silicate vitrification and rapid structural annealing.
Date: December 1, 1982
Creator: Porter, D. L.
Object Type: Report
System: The UNT Digital Library

[Eiband's]

Photograph of the Eiband's (located at 2201 Ave E) in Galveston, Texas.
Date: December 1, 1982
Creator: Texas Historical Commission
Object Type: Photograph
System: The Portal to Texas History

[Eiband's Texas Building & US National Bank]

Photograph of the Eiband's Texas Building & US National Bank (located at 22nd St & Church) in Galveston, Texas.
Date: December 1, 1982
Creator: Texas Historical Commission
Object Type: Photograph
System: The Portal to Texas History
Energy and Technology Review (open access)

Energy and Technology Review

Individual abstracts were prepared for the three items in this issue. These include age estimation of the universe, measurement of equations of state for tantalum, and inertial confinement fusion. (GHT)
Date: December 1, 1982
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Enertech 15-kW wind-system development. Phase II. Fabrication and test (open access)

Enertech 15-kW wind-system development. Phase II. Fabrication and test

This Phase II report presents a description of the Enertech 15 kW prototype wind system hardware fabrication; results of component tests; and results of preliminary testing conducted at Norwich, VT and the RF Wind Energy Research Center. In addition, the assembly sequence is documented. During testing, the unit experienced several operational problems, but testing proved the design concept and demonstrated the system's ability to meet the contract design specifications for power output.
Date: December 1, 1982
Creator: Zickefoose, C.R.
Object Type: Report
System: The UNT Digital Library
Enhanced selective hydrogen desorption from metals (open access)

Enhanced selective hydrogen desorption from metals

The thermal desorption of hydrogen isotopes from a metal is usually a second order process, the rate for which becomes asymptotically slow. We present a method for enhancing the desorption rate of one particular isotope by maintaining a constant pressure of another molecular species. This results in an effective first order desorption and concomitant exponential decay of the concentration of the selected isotope. Data are presented for the enhanced desorption of deuterium from a Zr-Al getter. The results agree well with a theoretical model, which is discussed. This enhanced desorption method should be particularly useful for tritium operation in the Tokamak Fusion Test Reactor.
Date: December 1, 1982
Creator: Knize, R. J. & Cecchi, J. L.
Object Type: Report
System: The UNT Digital Library
Environmental and radiological safety studies: interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, July 1-September 30, 1982 (open access)

Environmental and radiological safety studies: interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, July 1-September 30, 1982

Although existing radioisotope thermoelectric generator designs have proved more than adequately safe, more information is continually sought about the heat sources to improve their safety. The work here includes studies of the effects on the heat sources of terrestrial and aquatic environments and also of the effects of the heat sources on various simulated environments. This progress report presents recent data from environmental chamber and aquatic experiments and gives the present status of the experiments.
Date: December 1, 1982
Creator: Matlack, G. M.; Patterson, J. H. & Stalnaker, N. D.
Object Type: Report
System: The UNT Digital Library
Estimating tail probabilities (open access)

Estimating tail probabilities

This paper investigates procedures for univariate nonparametric estimation of tail probabilities. Extrapolated values for tail probabilities beyond the data are also obtained based on the shape of the density in the tail. Several estimators which use exponential weighting are described. These are compared in a Monte Carlo study to nonweighted estimators, to the empirical cdf, to an integrated kernel, to a Fourier series estimate, to a penalized likelihood estimate and a maximum likelihood estimate. Selected weighted estimators are shown to compare favorably to many of these standard estimators for the sampling distributions investigated.
Date: December 1, 1982
Creator: Carr, D. B. & Tolley, H. D.
Object Type: Report
System: The UNT Digital Library
Evaluation of experiences in long-term radon and radon-daughter measurements (open access)

Evaluation of experiences in long-term radon and radon-daughter measurements

Pacific Northwest Laboratory (PNL) is performing side-by-side measurements of radon and radon daughter concentrations using several instruments and techniques, and is comparing these measurements with side-by-side measurements made by other investigators at other locations. The standard deviation of the differences between the (natural) logarithms of the Terradex Track Etch radon concentrations and the logarithms of the Radon Progency Integrating Sampling Units (RPISU) radon daughter concentrations (S.D.-ln) measured in 50 buildings in Edgemont, South Dakota, was 0.37. Using this S.D.-ln, it can be calculated that if the Track Etch radon daughter concentration is 0.010 WL there should be only a 14% probability that the RPISU average would be greater than 0.015 WL, and only a 3% probability tht the RPISU average would be greater than 0.020 WL. If buildings had been cleared from remedial action when the Track Etch averages were less than 0.10 WL, then about 61% of the buildings would have been cleared from remedial action, and only a few percent of these buildings would have actually had average RPISU concentrations greater than 0.015 WL. The S.D.-ln between the Track Etch radon measurements and the RPISU radon daughter measurements made by ALARA at Grand Junction, the PERM radon measurements …
Date: December 1, 1982
Creator: Young, J. A.; Jackson, P. O. & Thomas, V. W.
Object Type: Report
System: The UNT Digital Library
Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor (open access)

Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports.
Date: December 1, 1982
Creator: Miller, R. L. & Adams, J. A.
Object Type: Report
System: The UNT Digital Library
Evaluation of structural integrity of IPNS-I and ZING-P' targets (open access)

Evaluation of structural integrity of IPNS-I and ZING-P' targets

This report discusses the design, production, and evaluation of clad uranium-alloy targets that function as spallation neutron sources in the ZING-P' and IPNS-I facilities with a pulsed (10 to 30 Hz), 500-MeV proton beam. The methodology and results of theoretical nuclear-particle transport, heat transport, and stress analyses that were used in the development of a design for the targets are described. The production of a zirconium-clad uranium-alloy cylinder for ZING-P' and Zircaloy-2-clad uranium-alloy discs for IPNS-I is discussed with particular attention to the procedural details. The theoretical analyses were verified by measuring the thermal and mechanical response of the clad uranium under conditions designed to simulate the operations of the pulsed-neutron sources.
Date: December 1, 1982
Creator: Carpenter, J.; Ahmed, H.; Loomis, B.; Ball, J.; Ewing, T.; Bailey, J. et al.
Object Type: Report
System: The UNT Digital Library
Evaluation of the Beijing Instrument Factory GDB-52LD photomultiplier (open access)

Evaluation of the Beijing Instrument Factory GDB-52LD photomultiplier

Characteristics have been measured for the GDB-52LD 2''-diameter photomultiplier. Some typical photomultiplier characteristics -- such as gain, dark current, anode output current, transit and rise times as a function of voltage between anode and cathode, and photoelectron pulse-height spectrum, the quantu-efficiency, and the single-electron transit time spread were measured. Descriptions of the measuring systems were also given.
Date: December 1, 1982
Creator: Young, E. & Lo, C.C.
Object Type: Report
System: The UNT Digital Library
Evaluation of the /sup 238/U neutron total cross section (open access)

Evaluation of the /sup 238/U neutron total cross section

Experimental energy-averaged neutron total cross sections of /sup 238/U were evaluated from 0.044 to 20.0 MeV using regorous numerical methods. The evaluated results are presented together with the associated uncertainties and correlation matrix. They indicate that this energy-averaged neutron total cross section is known to better than 1% over wide energy regions. There are somwewhat larger uncertainties at low energies (e.g., less than or equal to 0.2 MeV), near 8 MeV and above 15 MeV. The present evaluation is compard with values given in ENDF/B-V.
Date: December 1, 1982
Creator: Smith, A.; Poenitz, W.P. & Howerton, R.J.
Object Type: Report
System: The UNT Digital Library
Evaluation of unthrottled combustion system options for light duty applications with future syncrude derived fuels. Alternative Fuels Utilization Program (open access)

Evaluation of unthrottled combustion system options for light duty applications with future syncrude derived fuels. Alternative Fuels Utilization Program

An experimental program examining the interaction between several fuel and light duty automotive engine combinations is detailed. Combustion systems addressed covered indirect and direct injection diesel and spark ignited stratified charge. Fuels primarily covered D2, naphtha and intermediate broadcut blends. Low ignition quality diesel fuels were also evaluated. The results indicate the baseline fuel tolerance of each combustion system and enable characteristics of the systems to be compared. Performance, gaseous and particulate emissions aspects were assessed. The data obtained assists in the selection of candidate combustion systems for potential future fuels. Performance and environmental penalties as appropriate are highlighted relative to the individual candidates. Areas of further work for increased understanding are also reviewed.
Date: December 1, 1982
Creator: Needham, J. R.; Cooper, B. M. & Norris-Jones, S. R.
Object Type: Report
System: The UNT Digital Library
Expectations for old and new physics at high energy colliders (open access)

Expectations for old and new physics at high energy colliders

During the past year, the first data from the SPS collider at CERN have become available. The initial results are only a glimpse at a new energy regime and we can reasonably expect an increase in the extent of the data by a factor of 10/sup 4/ to 10/sup 5/. Moreover, within a few years, the Fermilab Tevatron Collider will be in operation with a center of mass energy nearly four times as great as that at CERN. Beyond these machines are other possibilities: a high luminosity pp machine at Brookhaven with a center of mass energy of 0.8 TeV; a p anti p or pp machine in the LEP tunnel at CERN; a desetron in the southwestern United States with many TeV in the center of mass. The purpose of these lectures is to provide an orientation for the wealth of data that these machines will provide.
Date: December 1, 1982
Creator: Cahn, R.N.
Object Type: Article
System: The UNT Digital Library
Experimental study of a fiber absorber-suppressor modified Trombe wall (open access)

Experimental study of a fiber absorber-suppressor modified Trombe wall

An experimental study has been conducted to ascertain the effects of introducing fiber bed absorbers on Trombe wall passive solar collectors. Two identical, Trombe wall passive solar units were constructed that incorporate the basic components of masonry collector-storage walls: glazings, masonry and thermal insulation. Both units were extensively instrumented with thermocouples and heat flux transducers. Ambient temperature, relative humidity, wind speed and insolation are also measured. In the first part of the study the two Trombe wall units were tested with a single glass cover. The thermal performance of both units was found to be virtually identical. In the second part of the study a single cover Trombe wall unit was compared with a double cover unit and the latter was found to have higher air gap and masonry wall temperatures and heat fluxes. In the final phase of the experiment, an absorbing, scattering and emitting fiberglass-like material was placed in the air gap of the single gazed wall. Tests were conducted to compare the solar-thermal performance, heat loss and gain characteristics between the units with and without the fiber absorber-suppressor. This experiment showed that the fiber bed served to decouple the wall at night from its exterior environment and …
Date: December 1, 1982
Creator: Choudhury, D & Birkebak, R C
Object Type: Report
System: The UNT Digital Library
Experimental Verification of a Cracked Fuel Mechanical Model (open access)

Experimental Verification of a Cracked Fuel Mechanical Model

This report describes the results of a series of laboratory experiments conducted to independently verify a model that describes the nonlinear mechanical behavior of cracked fuel in pelletized UO{sub 2}/Zircaloy nuclear fuel rods under normal operating conditions. After a brief description of the analytical model, each experiment is discussed in detail. Experiments were conducted to verify the general behavior and numerical values for the three primary independent modelling parameters (effective crack roughness, effective gap roughness, and total crack length), and to verify the model predictions that the effective Young's moduli for cracked fuel systems were substantially less than those for solid UO{sub 2} pellets. In general, the model parameters and predictions were confirmed, and new insight was gained concerning the complexities of cracked fuel mechanics.
Date: December 1, 1982
Creator: Williford, R. E.
Object Type: Report
System: The UNT Digital Library
Fast-neutron scattering cross sections of elemental zirconium (open access)

Fast-neutron scattering cross sections of elemental zirconium

Differential neturon-elastic-scattering cross sections of elemental zirconium are measured from 1.5 to 4.0 MeV at intervals of less than or equal to 200 keV. Inelastic-neutron-scattering cross sections corresponding to the excitation of levels at observed energies of: 914 +- 25, 1476 +- 37, 1787 +- 23, 2101 +- 26, 2221 +- 17, 2363 +- 14, 2791 +- 15 and 3101 +- 25 keV are determined. The experimental results are interpreted in terms of the optical-statistical model and are compared with corresponding quantities given in ENDF/B-V.
Date: December 1, 1982
Creator: Smith, A. B. & Guenther, P. T.
Object Type: Report
System: The UNT Digital Library
Field test and evaluation of the IAEA coincidence collar for the measurement of unirradiated BWR fuel assemblies (open access)

Field test and evaluation of the IAEA coincidence collar for the measurement of unirradiated BWR fuel assemblies

The neutron coincidence counter has been field tested and evaluated for the measurement of boiling-water-reactor (BWR) fuel assemblies at the ASEA-ATOM Fuel Fabrication Facility. The system measures the /sup 235/U content per unit length of full fuel assemblies using neutron interrogation and coincidence counting. The /sup 238/U content is measured in the passive mode without the AmLi neutron interrogatioin source. The field tests included both standard production movable fuel rods to investigate enrichment and absorber variations. Results gave a response standard deviation of 0.9% for the active case and 2.1% for the passive case in 1000-s measurement times. 10 figures, 2 tables.
Date: December 1, 1982
Creator: Menlove, H. O. & Keddar, A.
Object Type: Report
System: The UNT Digital Library
Field tests and evaluations of the IAEA Active-Well Coincidence Counter (open access)

Field tests and evaluations of the IAEA Active-Well Coincidence Counter

This report summarizes and evaluates field tests of the Active Well Coincidence Counter (AWCC) at Winfrith and Dounreay, United Kingdom. The applicability of the AWCC for assaying the uranium content of a wide variety of materials was demonstrated and calibration curves were generated. The AWCC was used in three modes (fast, thermal, and passive) while assaying powders, pellets, cartridges, plates, assorted residues, and materials-testing-reactor fuel assemblies.
Date: December 1, 1982
Creator: Krick, M. S. & Rinard, P. M.
Object Type: Report
System: The UNT Digital Library
The first reactor [40th anniversary commemorative edition] (open access)

The first reactor [40th anniversary commemorative edition]

This updated and revised story of the first reactor, or 'pile,' commemorates the 40th anniversary of the first controlled, self-sustaining nuclear chain reaction created by mankind. Enrico Fermi and his team of scientists initiated the reaction on December 2, 1941, underneath the West Stands of Stagg Field at the University of Chicago. Firsthand accounts of the participants as well as postwar recollections by Enrico and Laura Fermi are included.
Date: December 1, 1982
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Fiscal implications of a 1-mill/kWh waste management fee (open access)

Fiscal implications of a 1-mill/kWh waste management fee

The variations in parameters and uncertainties that can affect future waste management program costs are examined. Costs were estimated for both spent fuel and reprocessing waste disposal. Costs for repository site exploration and development, construction and operation of the first two repositories, and waste transportation of either spent fuel or reprocessing waste to the repository were included in the estimate of program costs. Costs for disposing of either spent fuel or reprocessing wastes in four generic geologic media (domed salt, bedded salt, tuff, and granite) were estimated considering uncertainties in package design waste preparation, mining cost, repository layout, repository startup date, and waste shipment distance. The range of these costs is then compared with estimated revenues from the proposed 1-mill/kWh fee to determine whether that fee would provide sufficient funds to meet waste management program needs. The estimated revenues and the range of program cost estimates in 1982 dollar resulting from these variations and uncertainties are shown graphically. The figure shows that the assumed 1-mill/kWh fee provides sufficient revenues to meet program costs for the range of conditions considered. Collection of a 1-mill/kWh fee at the time fuel is irradiated will result in the federal government precollecting for future waste …
Date: December 1, 1982
Creator: Engel, R. L. & White, M. K.
Object Type: Report
System: The UNT Digital Library
Fission-suppressed hybrid reactor: the fusion breeder (open access)

Fission-suppressed hybrid reactor: the fusion breeder

Results of a conceptual design study of a /sup 233/U-producing fusion breeder are presented. The majority of the study was devoted to conceptual design and evaluation of a fission-suppressed blanket and to fuel cycle issues such as fuel reprocessing, fuel handling, and fuel management. Studies in the areas of fusion engineering, reactor safety, and economics were also performed.
Date: December 1, 1982
Creator: Moir, R. W.; Lee, J. D. & Coops, M. S.
Object Type: Report
System: The UNT Digital Library
Flight Systems Safety Program Progress Report: August 1982 (open access)

Flight Systems Safety Program Progress Report: August 1982

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.
Date: December 1, 1982
Creator: Bronisz, S. E.
Object Type: Report
System: The UNT Digital Library