Aerial gamma ray and magnetic survey: Mississippi and Florida airborne survey, Tupelo quadrangle, Mississippi, Alabama, and Tennessee. Final report (open access)

Aerial gamma ray and magnetic survey: Mississippi and Florida airborne survey, Tupelo quadrangle, Mississippi, Alabama, and Tennessee. Final report

The Tupelo quadrangle covers a region immediately east of the Mississippi River flood plain in the northernmost Gulf Coastal Physiographic Province. Sediments of Teritary and Paleozoic basins shoal eastward. Tertiary exposures dominate the western half of the quadrangle. Cretaceous strata are exposed over most of the eastern half. A search of available literature revealed no known uranium deposits. A total of eighty-six uranium anomalies were detected and are discussed briefly. Few were considered significant, and most appear to relate to some cultural feature. Magnetic data appears, for the most part, to be in agreement with existing structural interpretations of the region.
Date: September 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962 (open access)

Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962

Progress is reported on thermonuclear research. Separate abstracts were prepared for 8 of the 10 sections. Design and engineering service reports and notes are given in the remaining sections. (M.C.G.)
Date: September 12, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Writer's Guide for technical procedures (open access)

Writer's Guide for technical procedures

A primary objective throughout the Department of Energy (DOE) complex is that operations be conducted in a deliberate and controlled manner with emphasis upon recognition and maintenance of the facility-specific safety envelope. One critical element of maintaining the safety envelope is procedures. DOE is providing guidance through this and other writer's guides to assist procedure writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations in keeping with such DOE Orders as 5480.19, Conduct of Operations for DOE Facilities'', 5480.5, Safety of Nuclear facilities'', and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors''. This Writer's Guide addresses the content, format, and style of technical procedures (procedures that prescribe production, operation of equipment and facilities, and maintenance activities) and is intended to be applied in a manner appropriate to the individual facility, 15 refs.
Date: September 1, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Performance and development of dE/dx counters (open access)

Performance and development of dE/dx counters

The performance of existing or nearly completed detectors for particle identification by using the relativistic rise of energy loss will be discussed. Detailed analysis of systematic errors leads finally to large detector systems approaching the ultimate resolution as measured in small test devices. New methods for extracting the information from the counter with the potential of better particles separation than standard dE/dx will be presented. It includes very fine sampling, delta-ray clipping, and cluster counting.
Date: September 1, 1980
Creator: Walenta, A. H.
Object Type: Article
System: The UNT Digital Library
Water assessment report, section 13(b) (open access)

Water assessment report, section 13(b)

An assessment is presented of water requirements and water supply availability for a proposed Geothermal Binary Demonstration Electric Generation Project near Heber, California. The following topics are discussed: principal findings, project description, water supply and availability, and effects of the project. (MHR)
Date: September 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Methanation in catalyst-sprayed tube wall reactors: a review (open access)

Methanation in catalyst-sprayed tube wall reactors: a review

The design and operation of catalyst-sprayed tube wall reactors for methanation are discussed. Reactor tubes were either coated on the inner surface or on the outer surface with a Raney nickel catalyst. A liquid coolant, which was opposite the catalyst-reactant gas-side, removed the heat of methanation. Catalyst performance, reactor operating conditions, spent catalyst analyses, and other results are presented for five PDU tests.
Date: September 1, 1980
Creator: Pennline, H. W.; Schehl, R. R.; Haynes, W. P. & Forney, A. J.
Object Type: Report
System: The UNT Digital Library
Proposed research on advanced accelerator concepts (open access)

Proposed research on advanced accelerator concepts

This report summarizes technical progress and accomplishments during the proposed three-year research on advanced accelerator concepts supported by the Department of Energy under Contract No. DE-FG02-88ER40465. A vigorous theoretical program has been pursued in critical problem areas related to advanced accelerator concepts and the basic equilibrium, stability, and radiation properties of intense charged particle beams. Broadly speaking, our research has made significant contributions in the following three major areas: Investigations of physics issues related to particle acceleration including two-beam accelerators and cyclotron resonance laser (CRL) accelerators; Investigations of RF sources including the free- electron lasers, cyclotron resonance masers, and relativistic magnetrons; Studies of coherent structures in electron plasmas and beams ranging from a low-density, nonrelativistic, pure electron plasma column to high-density, relativistic, non-neutral electron flow in a high-voltage diode. The remainder of this report presents theoretical and computational advances in these areas.
Date: September 1, 1991
Creator: Davidson, R.C. & Wurtele, J.S.
Object Type: Report
System: The UNT Digital Library
Commercial US nuclear reactors and waste: the current status (open access)

Commercial US nuclear reactors and waste: the current status

Between March 1 and June 15, 1980, the declared size of the commercial light waste reactor (LWR) nuclear power industry in the US has decreased another 9 GWe. For the presently declared size: the 165 declared reactors will peak at a capacity of 153 GWe in 2001 and will consume about 870,000 MTU as enrichment feed; the theoretical rate of enrichment requirements will peak at about 19,000,000 SWUs/y in the year 2014; as few as two repositories each with capacity equivalent to 100,000 MTU would hold the waste; and predisposal storage reactor basins and AFRs (away-from-reactor basins) would peak at <85,000 MTU in the year 2020 if the two respositories were commissioned in the years 1997 and 2020. It should be noted that the number of declared LWRs has dropped from 226 on December 31, 1974 to 165 as of this writing. The oil equivalent of the energy loss, assuming a 50% efficiency in use as in cars, is 17,000 million barrels. This is about 10 years of the current rate of US consumption of OPEC oil.
Date: September 1, 1980
Creator: Platt, A.M. & Robinson, J.V.
Object Type: Report
System: The UNT Digital Library
CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961 (open access)

CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from granite, solvent extraction technology, mechanisms of separation processes, radiation effects on catalysts, ion exchange technology, chemical engineering research, chemical applications of nuclear explosions, reactor evaluation studies, and assistance programs. (J.R.D.)
Date: September 21, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Liquefaction of coals using ultra-fine particle, unsupported catalysts: In situ generation by rapid expansion of supercritical fluid solutions (open access)

Liquefaction of coals using ultra-fine particle, unsupported catalysts: In situ generation by rapid expansion of supercritical fluid solutions

The purpose of this program is to design and fabricate an experimental ultra-fine particle generation system; use this system to generate ultra-fine, iron compound, catalyst particles; and to access the ability of these ultra-fine catalyst particles to improve the performance of the solubilization stage of two-stage, catalytic-catalytic liquefaction processes. The effort applied to this program during this reporting period was devoted to experimental design and fabrication tasks.
Date: September 1, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
A cryogenic system design for the international thermonuclear experimental reactor (ITER) (open access)

A cryogenic system design for the international thermonuclear experimental reactor (ITER)

A conceptual design for ITER was completed last year. The author developed a suitable cryogenic system for ITER as part of this conceptual design effort. An overview of the design is reported. Emphasis is on the fact that cryogenics is a mature science, and a system supporting ITER needs can be made from time-proven components without loss of efficiency or reliability. Because of the large size of the ITER cryogenic system, large numbers of compressors and expanders must be used. Very high reliability is assured by arranging these components in parallel banks where servicing of individual components can be done without interruption of operations. This and other ideas based on the author's experience with Mirror Fusion Test Facility (MFTF) operations are described. 5 refs., 3 figs.
Date: September 25, 1991
Creator: Slack, D.S.
Object Type: Article
System: The UNT Digital Library
Theoretical aspects of solid state reactions in a mixed particulate ensemble and kinetics of lead zirconate formation (open access)

Theoretical aspects of solid state reactions in a mixed particulate ensemble and kinetics of lead zirconate formation

A theoretical analysis was carried out to estimate the quasi-steady-state external mass transport by lattice, surface and gaseous diffusion in terms of the stereologically measurable microstructural parameters of a mixed powder compact. It was shown that the gaseous transport can be described by a single dimensionless quantity termed sublimation transport modulus. Using these equations, the relative importance of the alternate external transport modes can be evaluated. Experimental work determined the reaction isotherms for the formation of lead zirconate from yellow PbO and monoclinic zirconia between 710/sup 0/C to 810/sup 0/C for two zirconia size distributions. The larger zirconia showed diffusion controlled shrinking core kinetics up to about 90 percent reaction while the smaller zirconia indicated a diffusion controlled spherical growth of up to 85 percent reaction after an instantaneous nucleation at a limited number of sites. The difference was attributed to the differences in the mixing time and not to the particulate sizes. It was observed that for the same size range, a longer mixing operation gave a better dispersion of reactants which resulted in a higher nucleation site density required for a shrinking core type of product morphology and faster kinetics. A microprobe profile analysis of partially reacted particles …
Date: September 1, 1979
Creator: Chandratreya, S.S.
Object Type: Report
System: The UNT Digital Library
Tar sand extraction by steam stimulation and steam drive: measurement of physical properties (open access)

Tar sand extraction by steam stimulation and steam drive: measurement of physical properties

The measurement of the following thermophysical properties of Utah tar sands is in progress: thermal conductivity, specific heat relative permeability, and viscosity (of the recovered bitumen). During the report period (October 1, 1978 to November 1, 1979), experimental procedures have been developed and a basic data set has been measured. Additionally, standard core analysis has been performed for four drill sites in the Asphalt Ridge, Utah area.
Date: September 10, 1980
Creator: Linberg, W.R.
Object Type: Report
System: The UNT Digital Library
Energy Matrices of the f$sup 5$ Electron Configuration (open access)

Energy Matrices of the f$sup 5$ Electron Configuration

The complete electrostatic and spin-orbit matrices of the f/sup 5/ electron configuration were calculated and are presented tabularly. (auth)
Date: September 1, 1962
Creator: Wybourne, B. G.
Object Type: Report
System: The UNT Digital Library
Linear accelerator driven (LADR) and regenerative reactors (LARR) for nuclear non-proliferation (open access)

Linear accelerator driven (LADR) and regenerative reactors (LARR) for nuclear non-proliferation

Linear accelerator breeders (LAB) could be used to produce fissile fuel in two modes, either with fuel reprocessing or without fuel reprocessing. With fuel reprocessing, the fissile material would be separated from the target and refabricated into a fuel element for use in a burner power reactor. Without reprocessing, the fissile material would be produced in-situ, either in a fresh fuel element or in a depleted or burned element after use in a power reactor. In the latter mode the fissile material would be increased in concentration for reuse in a power reactor. This system is called a Linear Accelerator Regenerative Reactor (LARR). The LAB can also be conceived of operating in a power production mode in which the spallation neutrons would be used to drive a subcritical assembly to produce power. This is called a Linear Accelerator Driven Reactor (LADR). A discussion is given of the principles and some of the technical problems of both types of accelerator breeders.
Date: September 1, 1977
Creator: Steinberg, M.; Takahashi, H.; Powell, J. R. & Kouts, H. J.C.
Object Type: Report
System: The UNT Digital Library
Alternate materials of construction for geothermal applications. Progress report No. 14, July--September 1977 (open access)

Alternate materials of construction for geothermal applications. Progress report No. 14, July--September 1977

A program to determine if non-metallic materials such as polymers, concrete polymer composites, and refractory cements can be utilized as materials of construction in geothermal processes is in progress. To date, several high temperature polymer concrete systems have been formulated, laboratory and field tests performed in brine, flashing brine, and steam at temperatures up to 260/sup 0/C (500/sup 0/F), and economic studies started. Laboratory data for exposure times > 2 years are available. Results are also available from field exposures of up to 18 months in four geothermal environments. Good durability is indicated. Work at four of these sites is continuing.
Date: September 1, 1977
Creator: Kukacka, L. E.; Fontana, J.; Zeldin, A.; Sugama, T.; Horn, W.; Carciello, N. et al.
Object Type: Report
System: The UNT Digital Library
Annual Report on Wildlife Activities, 1985 Fiscal Year, Action Item 40.1, Columbia River Basin Fish and Wildlife Program. (open access)

Annual Report on Wildlife Activities, 1985 Fiscal Year, Action Item 40.1, Columbia River Basin Fish and Wildlife Program.

The report presents a brief synopsis and discussion of wildlife activities undertaken by Bonneville Power Administration. The objectives of the program were wildlife protection, mitigation, and enhancement planning; and implementation of actions to protect, mitigate, and enhance wildlife affected by development and operation of hydroelectric facilities in the Columbia River Basin. (ACR)
Date: September 1985
Creator: United States. Bonneville Power Administration. Division of Fish and Wildlife.
Object Type: Report
System: The UNT Digital Library
Geothermal technology publications and related reports: a bibliography, January 1984-December 1985 (open access)

Geothermal technology publications and related reports: a bibliography, January 1984-December 1985

Technological limitations restrict the commercial availability of US geothermal resources and prevent effective evaluation of large resources, as magma, to meet future US needs. The US Department of Energy has asked Sandia to serve as the lead laboratory for research in Geothermal Technologies and Magma Energy Extraction. In addition, technology development and field support has been provided to the US Continental Scientific Drilling Program. Published results for this work from January 1984 through December 1985 are listed in this bibliography.
Date: September 1, 1986
Creator: Cooper, D.L. (ed.)
Object Type: Report
System: The UNT Digital Library
Comparison of TRAC and RELAP5 reactor system calculations for a DEGB LOCA in K-14. 1 (open access)

Comparison of TRAC and RELAP5 reactor system calculations for a DEGB LOCA in K-14. 1

A comparison of TRAC and RELAP5 predictions of steady-state and DEGB LOCA results (FI phase) for K-14.1 has been made. Both codes had been previously benchmarked against 1985 L Reactor AC Flow data and were under configuration control. The purpose of the code-to-code comparison is to provide insight on the transient uncertainty in TRAC plenum and tank bottom plenum pressures. The comparisons focus on LOCA results between 0.5 and 2.0 s, which is the primary period of interest for Flow Instability (FI) limits.
Date: September 1, 1990
Creator: Griggs, D.P. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Liebmann, M.L. (Wais and Associates (United States))
Object Type: Report
System: The UNT Digital Library
Prototype arc saw design and cutting trials (open access)

Prototype arc saw design and cutting trials

A program was initiated to develop the arc saw as a tool capable of removing the end fittings from spent nuclear fuel bundles. A special arc saw for this purpose was designed, installed at the Pacific Northwest Laboratory and satisfactorily operated to remove end fittings from simulated, nonradioactive fuel bundles. The design of the arc saw included consideration of the cutting environment, power supply size, control equipment, and work piece size. Several simulated fuel bundles were cut to demonstrate that the arc saw met design specifications. Although the arc saw development program was curtailed before significant performance data could be collected, tests indicate that the arc saw is a good means of cropping spent fuel bundles and is well suited to remote operation and maintenance.
Date: September 1, 1980
Creator: Allison, G.S.
Object Type: Report
System: The UNT Digital Library
Detectors for radiation dosimetry (open access)

Detectors for radiation dosimetry

For our purposes in this review, we note the following points: (1) for charged particle detection, these counters can be filled with any noble gas-quenching gas mixture that produces satisfactory electrical signals; (2) neutron counters, in which the neutrons are detected by their interaction with the specific filling of the chamber to yield an ionizing particle, require special gas mixtures containing /sup 3/He or BF/sub 3/, an alternative approach is to coat the inner surface of the cathode with a boron or lithium compound; (3) proportional counters are used if there is any need to discriminate between different types of radiation incident on the chamber by the magnitude of the ionizing energy retained within the sensitive volume of the counter; (4) proportional counters can operate at higher speeds than Geiger counters, typically up to 10/sup 7/ cts/sec versus less than 10/sup 5//sec for the Geiger counters; and (5) Geiger counters produce very large uniform pulses which can be scaled by very simple electronics, hence, they are often used in survey meters and other portable monitoring instruments.
Date: September 1, 1979
Creator: Perez-Mendez, V.
Object Type: Article
System: The UNT Digital Library
High beta capture and mirror confinement of laser produced plasmas. Semiannual report, April 1, 1977--September 30, 1977 (open access)

High beta capture and mirror confinement of laser produced plasmas. Semiannual report, April 1, 1977--September 30, 1977

The LITE research program is addressing two aspects of mirror confinement physics. ECRH heating of the confined LITE plasma is being investigated as a means for producing a local electrostatic well to trap cold ions within the plasma and provide DCLC stabilization without the energy drain effects obtained with a cold stabilizing stream. Concurrently, the heavy ion beam probe diagnostic being developed in LITE to experimentally measure the space potential within a minimum-B mirror plasma. During the period, 10-A beam injection focused on the target location has been achieved with the neutral beam source; investigations of hot ion building have been carried out with both a laser produced and a washer gun target; calculations modeling the ECRH stabilization have been performed, the experimental program defined, and preparations for the ECRH stabilization investigation undertaken; and the high current cesium source and high resolution electrostatic analyzer have been developed for the heavy ion beam probe. The physics of the ECRH stabilization model is studied, and conditions necessary to produce a local potential well for trapping cold ions are examined. An analysis of the stabilizing effect of this potential dip on the DCLC mode is presented. The heavy ion probe, under development for …
Date: September 1, 1977
Creator: Haught, A.F.; Tomlinson, R.G. & Ard, W.B.
Object Type: Report
System: The UNT Digital Library
Convective equilibrium and mixing-length theory for stellarator reactors (open access)

Convective equilibrium and mixing-length theory for stellarator reactors

In high ..beta.. stellarator and tokamak reactors, the plasma pressure gradient in some regions of the plasma may exceed the critical pressure gradient set by ballooning instabilities. In these regions, convective cells break out to enhance the transport. As a result, the pressure gradient can rise only slightly above the critical gradient and the plasma is in another state of equilibrium - ''convective equilibrium'' - in these regions. Although the convective transport cannot be calculated precisely, it is shown that the density and temperature profiles in the convective region can still be estimated. A simple mixing-length theory, similar to that used for convection in stellar interiors, is introduced in this paper to provide a qualitative description of the convective cells and to show that the convective transport is highly efficient. A numerical example for obtaining the density and temperature profiles in a stellarator reactor is given.
Date: September 1, 1985
Creator: Ho, D.D.M. & Kulsrud, R.M.
Object Type: Report
System: The UNT Digital Library
Seismic hazard evaluation for the high-flux isotope reactor (HFIR) Oak Ridge National Laboratory, Oak Ridge, Tennessee (open access)

Seismic hazard evaluation for the high-flux isotope reactor (HFIR) Oak Ridge National Laboratory, Oak Ridge, Tennessee

This study investigates the probabilistic hazard of earthquake-induced ground shaking at the HFIR facility, Oak Ridge, Tennessee. These results will be used to calculate plant response and potential effects in a Probabilistic Risk Assessment (PRA). For this purpose, several guidelines apply to this work. First, both the frequency of exceedance and the uncertainty in frequency of exceedance of various ground motion levels must be represented. These are required by the PRA so that the frequency and uncertainty of various possible plant states can be expressed. Second, there is a deliberate attempt to provide an unbiased distribution of frequencies of exceedance, i.e. to present results that are neither conservative nor unconservative. This is consistent with the goals of a PRA, to provide unbiased estimates of plant effects from which appropriate decisions (for instance about evaluating existing levels of seismic design) can be reached. Recent intensive studies of seismic hazard in the central and eastern United States (CEUS) have been completed by the Electric Power Research Institute (EPRI). These studies represent major efforts to characterize the seismic hazard for nuclear power plants in the CEUS, and use the most recent, up-to-date understandings of seismicity and ground motion relations for the region. With …
Date: September 1, 1991
Creator: McGuire, R.K. & Toro, G.R. (Risk Engineering, Inc., Golden, CO (United States))
Object Type: Report
System: The UNT Digital Library