24 Matching Results

Results open in a new window/tab.

Energy related studies utilizing microcline thermochronology: Progress report, May 1, 1987-April 30, 1988 (open access)

Energy related studies utilizing microcline thermochronology: Progress report, May 1, 1987-April 30, 1988

Rock samples from the Salton Sea Geothermal Field (sandstone, tuff, granite) and from accretionary prism sediments along the convergent margins in southeast Alaska and southwest Japan have been dated by the /sup 40/Ar/sup 39/Ar method. Paleotemperatures have been calculated. (ACR
Date: April 30, 1988
Creator: unknown
System: The UNT Digital Library
A 3 TeV on 3 TeV proton-proton dedicated collider for Fermilab (open access)

A 3 TeV on 3 TeV proton-proton dedicated collider for Fermilab

The Fermilab Dedicated Collider proposed in May 1983 is a 2 TeV on 2 TeV p)bar p) collider. The expected luminosity is )approximately) 10/sup 31/ cm/sup (minus/2)sec/sup )minus/1) and the estimated cost is )approximately) $362M (FY-83 dollars). Since 1983 both the superconducting magnet and the particle detector technologies have advanced and the countenance of physics, hence the desired characteristics of new facilities have also altered somewhat. We want to show here that with the new magnet technology used for the SSC one can construct a 3 TeV on 3 TeV pp collider on the Fermilab site. This pp Dedicated Collider )PPDC) will have a luminosity of about 10/sub 33/cm/sup )minus/2)sec)sup)minus)1) and a cost only )approximately) 50)percent) more than that of the p)bar p) Dedicated Collider. 3 figs
Date: March 30, 1988
Creator: Teng, L.C.
System: The UNT Digital Library
Interim report cyanide safety studies (open access)

Interim report cyanide safety studies

Over the past few years several proposals have been prepared to investigate the potential hazard of ferrocyanide-nitrate reactions that may occur in some Hanford waste tanks. In 1988 Westinghouse Hanford Company (WHC) decided to perform some of the suggested experimental work. Based on the proposal submitted in July, 1988, it was agreed to do a portion of the work during FY 1988. This report summarizes the results of that work, provides a preliminary analysis of the results, and includes recommendations for further study. The work completed consists of a brief literature search, preparation and analysis of several cesium nickel ferrocyanide, Cs{sub 2}NiFe(CN){sub 6}, oxdiation studies using Differential Scanning Calorimetry (DSC) and Thermogravimetry (TG), and small scale explosion tests.
Date: September 30, 1988
Creator: Burger, L.L. & Scheele, R.D.
System: The UNT Digital Library
Preconstruction of the Honey Lake Hybrid Power Plant (open access)

Preconstruction of the Honey Lake Hybrid Power Plant

The work undertaken under this Contract is the prosecution of the preconstruction activities, including preliminary engineering design, well field development, completion of environmental review and prosecution of permits, and the economic and financial analysis of the facility. The proposed power plant is located in northeastern California in Lassen County, approximately 25 miles east of the town of Susanville. The power plant will use a combination of wood residue and geothermal fluids for power generation. The plant, when fully constructed, will generate a combined net output of approximately 33 megawatts which will be sold to Pacific Gas and Electric Company (PG E) under existing long-term power sales contracts. Transfer of electricity to the PG E grid will require construction of a 22-mile transmission line from the power plant to Susanville. 11 refs., 12 figs., 7 tabs.
Date: April 30, 1988
Creator: unknown
System: The UNT Digital Library
Some continuously variable partial snakes of Type 1 and Type 2 (open access)

Some continuously variable partial snakes of Type 1 and Type 2

In order to obtain polarized beam in proton accelerators, Siberian snakes of two types may be needed in order to establish a spin tune independent of energy. We have done a numerical study to find a type II partial snake and to find more exact solutions for the type I partial snakes previously proposed. We find a type II partial snake. We find that the unequal field integrals needed to modify approximate type I snakes to exactly type I snakes with horizontal and vertical bends result in unacceptably large orbit excursions. We find a new type I snake with smaller field integrals at small overall rotation. An 8 magnet type II snake works from 0 to {pi} but more magnets might be used to reduce the excursion at small angle. Also, no type I partial snake with as few as 8 magnets has been found which will work continuously from 0 to {pi}. It appears that horizontal and vertical bends cannot provide solutions for pure type I or type II that allow the field integrals to approach zero as the rotation goes to zero. Versions of both the new type I and type II partial snakes are presently used as …
Date: November 30, 1988
Creator: Underwood, D.G.
System: The UNT Digital Library
Preconstruction of the Honey Lake Hybrid Power Plant: Final report (open access)

Preconstruction of the Honey Lake Hybrid Power Plant: Final report

The work undertaken under this Contract is the prosecution of the preconstruction activities, including preliminary engineering design, well field development, completion of environmental review and prosecution of permits, and the economic and financial analysis of the facility. The proposed power plant is located in northeastern California in Lassen County, approximately 25 miles east of the town of Susanville. The power plant will use a combination of wood residue and geothermal fluids for power generation. The plant, when fully constructed, will generate a combined net output of approximately 33 megawatts which will be sold to Pacific Gas and Electric Company (PGandE) under existing long-term power sales contracts. Transfer of electricity to the PGandE grid will require construction of a 22-mile transmission line from the power plant to Susanville. 11 refs., 12 figs., 4 tabs.
Date: April 30, 1988
Creator: unknown
System: The UNT Digital Library
Beta-delayed proton emission in neutron-deficient lanthanide isotopes (open access)

Beta-delayed proton emission in neutron-deficient lanthanide isotopes

Forty-two ..beta..-delayed proton precursors with 56less than or equal toZless than or equal to71 and 63less than or equal toNless than or equal to83 were produced in heavy-ion reactions at the Lawrence Berkeley Laboratory SuperHILAC and their radioactive decay properties studied at the on-line mass separation facility OASIS. Twenty-five isotopes and eight delayed proton branches were identified for the first time. Delayed proton energy spectra and proton coincident ..gamma..-ray and x-ray spectra were measured for all precursors. In a few cases, proton branching ratios were also determined. The precursor mass numbers were determined by the separator, while the proton coincident x-ray energies provided unambiguous Z identifications. The proton coincident ..gamma..-ray intensities were used to extract final state branching ratios. Proton emission from ground and isomeric states was observed in many cases. The majority of the delayed proton spectra exhibited the smooth bell-shaped distribution expected for heavy mass precursors. The experimental results were compared to statistical model calculations using standard parameter sets. Calculations using Nilsson model/RPA ..beta..-strength functions were found to reproduce the spectral shapes and branching ratios better than calculations using either constant or gross theory ..beta..-strength functions. Precursor half-life predictions from the Nilsson model/RPA ..beta..-strength functions were also in …
Date: September 30, 1988
Creator: Wilmarth, P.A.
System: The UNT Digital Library
Physics modeling support for the International Thermonuclear Experimental Reactor: Final report (open access)

Physics modeling support for the International Thermonuclear Experimental Reactor: Final report

There are two major sections to this report. The first section of the report is an executive summary of the work done this year. For each task, the major results are condensed for the reader's convenience. The major result of each memo, report or presentation is summarized briefly in this section. The second section of the report is a collection of appendices containing reports, memos, and presentations written this year. Here, the interested reader can investigate any topic discussed in the summary in more detail. The documentation is presented in chronological order, and we would like to note that the content of later documents may supercede that of earlier ones. The summaries are divided into sections, corresponding to the tasks outlined in the original proposal for the work. These sections are: MUMAK code development and application; Alfven wave stability problem; TETRA systems code development and application; lower hybrid heating and current drive; and advanced blanket modeling.
Date: September 30, 1988
Creator: unknown
System: The UNT Digital Library
Raman scattering in crystals (open access)

Raman scattering in crystals

A tutorial presentation is given of Raman scattering in crystals. The physical concepts are emphasized rather than the detailed mathematical formalism. Starting with an introduction to the concepts of phonons and conservation laws, the effects of photon-phonon interactions are presented. This interaction concept is shown for a simple cubic crystal and is extended to a uniaxial crystal. The correlation table method is used for determining the number and symmetry of the Raman active modes. Finally, examples are given to illustrate the relative ease of using this group theoretical method and the predictions are compared with measured Raman spectra. 37 refs., 17 figs., 6 tabs.
Date: September 30, 1988
Creator: Edwards, D.F.
System: The UNT Digital Library
Light-Weight Radioisotope Heater Unit Final Safety Analysis Report (LWRHU FSAR): Volume 3, Nuclear Risk Analysis Document (open access)

Light-Weight Radioisotope Heater Unit Final Safety Analysis Report (LWRHU FSAR): Volume 3, Nuclear Risk Analysis Document

The Light-Weight Radioisotope Heater Unit (LWRHU) Final Safety Analysis Report (FSAR), Volume 2, Accident Model Document (AMD) describes potential accident scenarios during the Galileo mission and evaluates the response of the LWRHUs to the associated accident environments. Any resulting source terms, consisting of PuO2 (with Pu-238 the dominant radionuclide), are then described in terms of curies released, particle size distribution, release location, and probabilities. This volume (LWRHU-FSAR, Volume 3, Nuclear Risk Analysis Document (NRAD)) contains the radiological analyses which estimate the consequences of the accident scenarios described in the AMD. It also contains the quantification of mission risks resulting from the LWRHUs based on consideration of all accident scenarios and their probabilities. Estimates of source terms and their characteristics derived in the AMD are used as inputs to the analyses in the NRAD. The Failure Abort Sequence Trees (FASTs) presented in the AMD define events for which source terms occur and quantify them. Based on this information, three types of source term cases (most probable, maximum, and expectation) for each mission phase were developed for use in evaluating the radiological consequences and mission risks. 4 refs., 5 figs., 8 tabs.
Date: November 30, 1988
Creator: unknown
System: The UNT Digital Library
Cost estimate for muddy water palladium production facility at Mound (open access)

Cost estimate for muddy water palladium production facility at Mound

An economic feasibility study was performed on the ''Muddy Water'' low-chlorine content palladium powder production process developed by Mound. The total capital investment and total operating costs (dollars per gram) were determined for production batch sizes of 1--10 kg in 1-kg increments. The report includes a brief description of the Muddy Water process, the process flow diagram, and material balances for the various production batch sizes. Two types of facilities were evaluated--one for production of new, ''virgin'' palladium powder, and one for recycling existing material. The total capital investment for virgin facilities ranged from $600,000 --$1.3 million for production batch sizes of 1--10 kg, respectively. The range for recycle facilities was $1--$2.3 million. The total operating cost for 100% acceptable powder production in the virgin facilities ranged from $23 per gram for a 1-kg production batch size to $8 per gram for a 10-kg batch size. Similarly for recycle facilities, the total operating cost ranged from $34 per gram to $5 per gram. The total operating cost versus product acceptability (ranging from 50%--100% acceptability) was also evaluated for both virgin and recycle facilities. Because production sizes studied vary widely and because scale-up factors are unknown for batch sizes greater than …
Date: November 30, 1988
Creator: McAdams, R.K.
System: The UNT Digital Library
Interim report cyanide safety studies (open access)

Interim report cyanide safety studies

Over the past few years several proposals have been prepared to investigate the potential hazard of ferrocyanide-nitrate reactions that may occur in some Hanford waste tanks. In 1988 Westinghouse Hanford Company (WHC) decided to perform some of the suggested experimental work. Based on the proposal submitted in July, 1988, it was agreed to do a portion of the work during FY 1988. This report summarizes the results of that work, provides a preliminary analysis of the results, and includes recommendations for further study. The work completed consists of a brief literature search, preparation and analysis of several cesium nickel ferrocyanide, Cs{sub 2}NiFe(CN){sub 6}, oxdiation studies using Differential Scanning Calorimetry (DSC) and Thermogravimetry (TG), and small scale explosion tests.
Date: September 30, 1988
Creator: Burger, L. L. & Scheele, R. D.
System: The UNT Digital Library
Development of core analysis procedures using x-ray computerized tomography. Quarterly report, September 1, 1988--November 30, 1988 (open access)

Development of core analysis procedures using x-ray computerized tomography. Quarterly report, September 1, 1988--November 30, 1988

In a letter from John C. Lorenz of Sandia National Laboratories dated November 8, 1988, analyses of interest included. With the core received, measurements are not possible. Core must be loaded into a passive vessel to flow various fluids for permeability measurements. Because the core was slabbed and plugged, this was not possible. Microfractures or porosity distribution can also be seen by flowing two fluids with contrasting attenuation coefficients and using a subtractive imaging technique. This again could not be done because core could not be inserted into a flow vessel. Similarly, fracture interconnections could not be measured. Each cross-sectional computerized tomography image is made up of a 256 {times} 256 array of data. This data array is composed of CT numbers which are collected from the scanner. These CT numbers are defined as normalized attenuation coefficients for the material being scanned. At the energy level used for this data, the CT numbers are approximately proportional to the density of the sample material. Subsequently, colors are, assigned arbitrarily to the CT numbers to highlight contrasts in density in the core. Red is assigned to higher-density regions and blue to lower density regions. Variations from red to blue are shown in …
Date: December 30, 1988
Creator: Sharer, J. C.
System: The UNT Digital Library
Rawlins UCG Demonstration Project. Final technical progress report, May 10, 1988--August 9, 1988 (open access)

Rawlins UCG Demonstration Project. Final technical progress report, May 10, 1988--August 9, 1988

The US Department of Energy and Energy International, Inc. have entered into a Cooperative Agreement to conduct a cost-shared field test demonstrating the operation of commercial-scale steeply dipping bed underground coal gasification (UCG) modules to provide the synthesis gas for a small-scale commercial ammonia plant. The field test and the commercial ammonia plant will be located near Rawlins, Wyoming. During this demonstration test, two or more modules will be operated simultaneously until one module is completely consumed and an additional module is brought on line. During this period, the average coal gasification rate will be between 500 and 1,200 tons per day. A portion of the raw UCC product gas. The UCG facility will continue to operate subsequent. to the demonstration to provide feedstock for the commercial plant. Energy International is responsible for accomplishing specific objectives in accordance with the Statement of Work by designing, installing, operating and monitoring the performance of the UCG modules as the feedstock source for the small-scale commercial ammonia plant. During this period, the project activities focused on project structuring, financing, and project management activities. Because the negotiations with investors were not completed on the schedule anticipated, adjustment of the schedule and activities was necessary. …
Date: November 30, 1988
Creator: unknown
System: The UNT Digital Library
Development of core analysis procedures using x-ray computerized tomography (open access)

Development of core analysis procedures using x-ray computerized tomography

In a letter from John C. Lorenz of Sandia National Laboratories dated November 8, 1988, analyses of interest included. With the core received, measurements are not possible. Core must be loaded into a passive vessel to flow various fluids for permeability measurements. Because the core was slabbed and plugged, this was not possible. Microfractures or porosity distribution can also be seen by flowing two fluids with contrasting attenuation coefficients and using a subtractive imaging technique. This again could not be done because core could not be inserted into a flow vessel. Similarly, fracture interconnections could not be measured. Each cross-sectional computerized tomography image is made up of a 256 {times} 256 array of data. This data array is composed of CT numbers which are collected from the scanner. These CT numbers are defined as normalized attenuation coefficients for the material being scanned. At the energy level used for this data, the CT numbers are approximately proportional to the density of the sample material. Subsequently, colors are, assigned arbitrarily to the CT numbers to highlight contrasts in density in the core. Red is assigned to higher-density regions and blue to lower density regions. Variations from red to blue are shown in …
Date: December 30, 1988
Creator: Sharer, J. C.
System: The UNT Digital Library
Aerated atomization of coal-water slurry fuels (open access)

Aerated atomization of coal-water slurry fuels

In order to observe the effects of rheology on the atomization of highly viscous non-Newtonian liquids, glycerin-water solutions and cellulose-glycerin-water solutions have been atomized. In this series of tests, nozzle pressure, air-liquid ratio and liquid viscosity were altered, and the effects were observed. 14 figs.
Date: September 30, 1988
Creator: Buckner, H.N.; Sojka, P.E. & Lefebvre, A.H.
System: The UNT Digital Library
Heat extraction in fractured hydrothermal reservoirs: Final report (open access)

Heat extraction in fractured hydrothermal reservoirs: Final report

The main objective of the Heat Extraction Project has been the development of means to estimate the thermal behavior of geothermal fluids from fractured hydrothermal resources based on production of mixed reservoir fluids from heat sweep by reinjected brine and resource fluid cooled by drawdown and infiltrating waters. Several reports and publications, listed in the concluding section of this report, resulted from the application of the SGP heat sweep model to achieve this objective. The Heat Extraction Project made major advances in the development of the 1-D Heat Sweep Model and its application in geothermal fields in several countries. Heat sweep joint studies are underway for reinjection evaluation at the Los Azufres, Los Humeros, and La Primavera fields in Mexico, for the 500 t/h reinjection test for the redevelopment program at Wairakei, New Zealand, for two hot water supply recirculation systems to be developed in the USSR, and for the phase 2 test at the Hot Dry Rock project at Fenton Hill, New Mexico. Advances were also made in the cooperative studies with CFE at Los Azufres on the evaluation of the effects of early operation of small wellhead generators on the reservoirs of potentially large geothermal fields. 9 refs., …
Date: June 30, 1988
Creator: Kruger, P.
System: The UNT Digital Library
Chloride content of Rocky Flats scrub alloy eleventh campaign solution following head end treatment (open access)

Chloride content of Rocky Flats scrub alloy eleventh campaign solution following head end treatment

A single batch of dissolver solution from the eleventh Rocky Flats Scrub Alloy (RFSA) campaign has been analyzed for chloride content following head end treatment to reduce its concentration. Scrub alloy buttons were dissolved in Tank 6.4D during May. In subsequent head end processing, chloride was precipitated with mercurous ion added as the nitrate. The precipitate, Hg{sub 2}Cl{sub 2}, was concurrently removed with the gelatin floc via centrifugation. Duplicate samples from Tank 11.2, containing the head end product, produced excellent agreement between their density measurements, acid analyses, and gross alpha activities, indicating them to be truly representative of the tank`s contents. Duplicate aliquots from each of these solutions were analyzed using the turbidimetric chloride method developed in the Separations Technology Laboratory. These resulted in an average chloride value of 41 ppm ({micro}g/mL) chloride for the head end product. Relative standard deviation of the measurement was {+-}4 ppm (n = 4), a precision of {+-}10%. Such a variance is normal at this low chloride level. Since initial chloride values prior to head end averaged 1455 ppm (0.041M), as analyzed by Laboratories Department, a chloride DF of approximately 35 was obtained. Such a reduced chloride level (to less than 100 ppm) in …
Date: June 30, 1988
Creator: Holcomb, H. P.
System: The UNT Digital Library
Committee on Interagency Radiation Research and Policy Coordination. Fourth annual report, July 1, 1987--June 30, 1988 (open access)

Committee on Interagency Radiation Research and Policy Coordination. Fourth annual report, July 1, 1987--June 30, 1988

This is the fourth annual report of the Committee on Interagency Radiation Research and Policy Coordination (CIRRPC). CIRRPC was chartered April 9, 1984 under the Federal Coordinating Council for Science, Engineering and Technology (FCCSET) and reports to the Office of Science and Technology Policy (OSTP), Executive Office of the President. Its overall charge is to coordinate radiation matters between agencies, evaluate radiation research, and provide advice on the formulation of radiation policy.
Date: June 30, 1988
Creator: Young, A.L.
System: The UNT Digital Library
Solvent problems in first PUREX cycle (open access)

Solvent problems in first PUREX cycle

In March, 1988, the first PUREX cycle suffered uranium contamination of the solvent, 30% TBP in n-paraffin. Initial indication of maloperation was uranium contamination of the plutonium product stream, 1BP. Uranium in relatively large quantities, 10{sup {minus}3} to 10{sup {minus}4} g/L, was found in the solvent in Tank 14.7. This tank contains first cycle solvent that has been through the solvent washing system and is destined for return back to the cycle. Solvent, contained in Tank 14.7 under normal operating conditions, has <1 {times} 10{sup {minus}4} g U/L following the carbonate-acid-carbonate washing sequence. Work at SRL showed that the interfacial tension of the contaminated solvent, as sampled, was 2.5, indicating that substances, possibly long chain acids, were present that could affect disengaging times for the solvent. Virgin 30% TBP in n-paraffin has a interfacial tension of around 10 or better, for example. Tests conducted by Reif also showed that the contaminated solvent picked up significantly more fission products, Ru{sup 106} and Zr{sup 95}, than did virgin solvent. The contaminated solvent, following contact with alumina, had a greatly improved interfacial tension of 9.5 and exhibited much less pickup of both Ru{sup 106} and Zr{sup 95}. In a H-Area process testing, contact …
Date: March 30, 1988
Creator: Holcomb, H. P.
System: The UNT Digital Library
Economic impacts study (open access)

Economic impacts study

This is a progress report on the first phase of a project to measure the economic impacts of a rapidly changing U.S. target base. The purpose of the first phase is to designate and test the macroeconomic impact analysis model. Criteria were established for a decision-support model. Additional criteria were defined for an interactive macroeconomic impact analysis model. After a review of several models, the Economic Impact Forecast System model of the U.S. Army Construction Research Laboratory was selected as the appropriate input-output tool that can address local and regional economic analysis. The model was applied to five test cases to demonstrate its utility and define possible revisions to meet project criteria. A plan for EIFS access was defined at three levels. Objectives and tasks for scenario refinement are proposed.
Date: September 30, 1988
Creator: Brunsen, W.; Worley, W. & Frost, E.
System: The UNT Digital Library
Ultraviolet-visible-near infrared spectra of 50 samples (open access)

Ultraviolet-visible-near infrared spectra of 50 samples

Under the subject contract, Unidynamics/Phoenix recorded the ultraviolet-visible-near infrared spectra of 50 samples supplied by LANL. A Varian Cary 2300 series spectrophotometer produced the spectral data. The spectrophotometer was interfaced to a Varian D5-15 Data Station, and hard copies of data were made. Baseline corrections throughout the wavelength range were established using Halon as a reference material. Corrected measurements were automatically made by the system on every sample. Two types of sample holders were tried. Before collecting data on the LANL samples, identical samples of PETN were examined using both holders.
Date: August 30, 1988
Creator: Taylor, B.
System: The UNT Digital Library
Health and Human Services Coordinating Council Annual Report:1988 (open access)

Health and Human Services Coordinating Council Annual Report:1988

Annual report of the Health and Human Services Coordinating Council describing goals, activities, and accomplishments during fiscal year 1988.
Date: November 30, 1988
Creator: Human and Health Services Coordinating Council
System: The Portal to Texas History
Drug Control (open access)

Drug Control

How to prevent the non-medical use of dependency-producing drugs has been a public policy concern for at least a century. A large part of the responsibility for controlling such substances has been assumed by the Federal Government. Historically based on decision to restrict availability through a system of close regulation, including selective prohibition, the current Federal anti-drugs strategy lives on activities and programs in five major areas: 1) regulation and other “enforcement” efforts; 2) support for international control and for control efforts of individual drug-producing and drug-transiting countries; 3) education and other prevention activities; 4 ) treatment and rehabilitation for drug-dependent persons; and ( 5 ) research on drugs , drug dependency, and prevention and treatment methods.
Date: September 30, 1988
Creator: Hogan, Harry L.
System: The UNT Digital Library