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5-Volt and 4.6 V plateaus in LiMn₂O₄ thin films

Description: Additional plateaus with median voltages of {similar_to}4.6 V, and {similar_to}5 V have been observed on charging thin film lithium batteries with crystalline LiMn{sub 2}O{sub 4} cathodes to 5.3 V. Total charge extracted from the 4 V and the two additional plateaus corresponded to about 1Li/Mn{sub 2}O{sub 4}, but the distribution of capacity among the three plateaus varied from film to film. It is speculated that the additional plateaus result from formation of mixed spinel structures in which a fraction of the 8a sites areoccupied by Mn{sup 2+} or Mn{sup 4+} ions and a fraction of the Li{sup +} ions occupy the 16d sites. After charging to 5.3 V, the 4.6 V plateau disappeared, and the capacity of the 4 V plateau increased at the expense of that of the 5 V plateau. The latter change is attributed to movement of Mn{sup 3+} or Mn{sup 5+} ions from 8a to 16d sites.
Date: January 1, 1996
Creator: Bates, J. B.; Lubben, D.; Dudney, N. J.; Zuhr, R. A. & Hart, F. X.
open access

45-day safety screening results and final report for Tank 241-BX-106, auger samples 95-AUG-049 and 95-AUG-050

Description: Two Auger Samples from tank 241-BX-106 were received at the 222-S Laboratory and underwent safety screening analyses - differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha analysis, and bulk density measurements - in accordance with the sampling and analysis plan.
Date: January 1, 1996
Creator: Sasaki, L.M.
open access

60-day waste compatibility safety issue and final results for 244-TX DCRT, grab samples TX-95-1, TX-95-2, and TX-95-3

Description: Three grab samples (TX-95-1, TX-95-2, and TX-95-3) were taken from tank 241- TX-244 riser 8 on November 7, 1995 and received by the 222-S Laboratory on that same day. Samples TX-95-1 and TX-95-2 were designated as supernate liquids, and sample TX-95-3 was designated as a supernate/sludge. These samples were analyzed to support the waste compatibility safety program. Accuracy and precision criteria were met for all analyses. No notifications were required based on sample results. This document provides the analysis to support the waste compatibility safety program.
Date: January 1, 1996
Creator: Esch, R.A.
open access

100KE/KW fuel storage basin surface volumetric factors

Description: This Supporting Document presents calculations of surface Volumetric factors for the 100KE and 100KW Fuel Storage Basins. These factors relate water level changes to basin loss or additions of water, or the equivalent water displacement volumes of objects added to or removed from the basin.
Date: January 1, 1996
Creator: Conn, K. R.
open access

1990 Activity report for 1986-1992

Description: As discussed in last year`s Activity Report, a fairly complete analysis of SPEAR problems was performed in concert with SLAC, and a major maintenance/improvement process was initiated in the spring of 1989. This run made it apparent that SPEAR will remain a very useful and impressive synchrotron radiation storage ring for at least a decade, given a steady maintenance and improvement program. More details about SPEAR functioning during the run, as well as SPEAR improvements, are contained in Chapter I. The formal SPEAR injector construction project was completed in November, 1990, on-time and on-budget. Although DOE was not able to provide anticipated FY90 commissioning funds, preliminary commissioning was performed and 2.3 GeV injection to SPEAR was demonstrated. A discussion of the Injector project is contained in Chapter II. Commissioning of the injector and the injector/SPEAR complex is continuing in 1991 with Users participating during the May-September period. This user participation allowed normal experimentation, so that systems could be tested critically, but with the commissioning process having higher priority than data acquisition. Another major event in 1990 was the full dedication of SPEAR to the synchrotron radiation program. Previously SPEAR was considered a high energy physics machine that was partially dedicated to synchrotron radiation. The full dedication means that the accelerator can be modified and improved for synchrotron radiation research. Despite the heavy emphasis on completing the Injector, many beam line improvements were achieved, as described in Chapter IV. Among these was the optimization of stations 6-2 and 10-2, the provision of a considerably larger hutch for Station 1-5, which contains the area detector diffractometer, and the introduction of white light capability on 10-2. The provision of good beam during the month of April made an appreciable amount of experimentation possible. These and other runs are described in Chapter VI.
Date: January 1, 1996
Creator: Cantwell, K.
open access

1995 Annual epidemiologic surveillance report for Brookhaven National Laboratory

Description: The US Department of Energy`s (DOE) conduct of epidemiologic surveillance provides an early warning system for health problems among workers. This program monitors illnesses and health conditions that result in an absence of five or more consecutive workdays, occupational injuries and illnesses, and disabilities and deaths among current workers. This report summarizes epidemiologic surveillance data collected from Brookhaven National Laboratory (BNL) from January 1, 1995 through December 31, 1995. The data were collected by a coordinator at BNL and submitted to the Epidemiologic Surveillance Data Center, located at Oak Ridge Institute for Science and Education, where quality control procedures and data analyses were carried out.
Date: 1996
open access

1995 Midnite Mine Radiation Survey

Description: Abstract: During the week of September 4, 1995, personnel from the U.S. Bureau of Mines conducted a Ra-226 survey at the Midnite Mine. One hundred thirty measurements were made on a rectangular grid with 150-m spacings. Concurrently, Shepherd Miller, Inc., took gross gamma readings in gR/h at the same grid points. In addition, the USBM collected 17 soil samples to be analyzed for radium, thorium, and potassium. The results of this survey are summarized in this report.
Date: 1996
Creator: Stroud, William P. & Droullard, Robert F.
open access

1996 environmental monitoring report for the Bettis Atomic Power Laboratory, Pittsburgh Site

Description: The 1996 results for the Bettis-Pittsburgh radiological and non-radiological environmental monitoring programs are presented. The primary mission of the Bettis Laboratory has been directed toward the design, development, testing, and operation of nuclear reactor propulsion plants for naval surface and submarine vessels. The results obtained from the monitoring programs demonstrate that the existing procedures ensured that releases to the environment during 1996 were in accordance with applicable federal, state, county, and local regulations. Evaluation of the environmental data indicated that the current operations at the Site continue to have no adverse effect on the quality of the environment. A conservative assessment of radiation exposure to the general public as a result of Site operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits established by the Environmental Protection Agency, the Nuclear Regulatory Commission and the US Department of Energy. A risk assessment of potentially exposed populations to chemical residues in the environment at the Site demonstrated that these residues do not pose any significant health risk.
Date: 1996
open access

3DTOM, Three-Dimensional Geophysical Tomography

Description: Abstract: 3DTOM is a DOS-compatible computer program developed by the Mines U.S. Bureau of for three-dimensional tomographic imaging of the subsurface at mine sites. The program uses the simultaneous iterative reconstruction technique (SIRT) to invert travel- time data and produce maps of wave velocity, or to invert amplitude data and generate maps of wave attenuation coefficients. Either seismic (compressional and/or shear) or electromagnetic (e.g., radio or radar) wave data may be used. Ray tracing in 3DTOM uses several different methods, including ray bending, network theory, and a combination of these. User-defined constraints are important in reducing the mathematical nonuniqueness of inversions based on limited data. 3DTOM permits the use of hard constraints, or soft constraints based on fuzzy logic, to allow for uncertainty in the constraints. Reliable subsurface images are useful in many different mine-related problems, including void detection, fracture detection, fluid monitoring, and qualitative stress evaluation.
Date: 1996
Creator: Jackson, Michael J. & Tweeton, Daryl R.
open access

Acceleration to collisions for the {mu}{sup +}-{mu}{sup {minus}} collider

Description: The authors discuss the problem of transforming muon beam bunches from a low-energy cooled state (E{sub {mu}} {approximately} 1 GeV) to short, high-energy bunches matched to high-energy collision conditions (E{sub {mu}} {approximately} 2 TeV). In this process the beam energy must increase by {approximately} three orders of magnitude, while the bunch length must be reduced by {approximately} two orders of magnitude (to {approximately} 3mm), while beam emittance dilution and beam losses, particularly through decay, must be minimized. From general considerations, they discuss possible acceleration scenarios including rapid-cycling synchrotron and recirculating linac options. The presently favored choice is a multi-stage recirculating linac system, which is discussed, and initial simulations of possible scenarios are presented. Future directions for development are discussed.
Date: January 1, 1996
Creator: Neuffer, D. V.
open access

Actinide extraction from ICPP sodium bearing waste with 0.75 M DHDECMP/TBP in Isopar L{reg_sign}

Description: Recent process development efforts at the Idaho Chemical Processing Plant include examination of solvent extraction technologies for actinide partitioning from sodium bearing waste (SBW) solutions. The use of 0.75 {und M} dihexyl-N, N-diethylcarbamoylmethylphosphonate (DHDECMP or simply CMP) and 1.0 {und M} tri-n-butyl phosphate (TBP) diluted in Isopar L{reg_sign} was explored for actinide removal from simulated SBW solutions. Experimental evaluations included batch contacts in radiotracer tests with simulated sodium bearing waste solution to measure the extraction and recovery efficiency of the organic solvent. The radioactive isotopes utilized for this study included Pu-238, Pu-239, Am-241, U-233, Np-239, Zr-95, Tc-99m, and Hg-203. Extraction contacts of the organic solvent with the traced SBW stimulant, strip (back-extraction) contacts of the loaded organic solvent with either a 1-hydroxyethane-1, 1-diphosphonic acid (HEDPA) in nitric acid solution or an oxalic acid in nitric acid solution, and solvent wash contacts with sodium carbonate were performed.
Date: January 1996
Creator: Herbst, R. S.; Brewer, K. N.; Garn, T. G.; Law, J. D.; Rodriguez, A. M. & Tillotson, R. T.
open access

Actinide partitioning studies using dihexyl-N,N-diethycarbamolymehtyl phosphonate and dissolved zirconium calcine

Description: A baseline flowsheet capable of partitioning the transuranic (TRU) elements from dissolved zirconium calcines has been developed. The goal of the TRU partitioning process is to remove the TRUs from solutions of dissolved zirconium calcines to below the 10 CFR 61.55 Class A waste limit of 10 nCi/g. Extraction, scrub, strip, and wash distribution coefficients for several elements, including the actinides, were measured in the laboratory by performing equal volume batch contacts. A solvent containing diheyl-N, N- diethylcarbamoylmethyl phosphonate (CMP), tributylphosphate (TBP), and a branched chain hydrocarbon as the diluent were used to develop this process. A non-radioactive zirconium pilot-plant calcine was spiked with the TRUs, U, Tc, or a radioactive isotope of zirconium to simulate the behavior of these elements in actual dissolved zirconium calcine feed. Distribution coefficient data obtained from laboratory testing were used to recommend: (1) solvent composition, (2) scrub solutions capable of selectively removing extracted zirconium while minimizing actinide recycle, (3) optimized strip solutions which quantitatively recover extracted actinides, and (4) feed adjustments necessary for flowsheet efficiency. Laboratory distribution coefficients were used in conjunction with the Generic TRUEX Model (GTM) to develop and recommend a flowsheet for testing in the 5.5-cm Centrifugal Contractor Mockup. GTM results indicate that the recommended flowsheet should remove the actinides from dissolved zirconium calcine feed to below the Class A waste limit of 10 nCi/g. Less than 0.01 wt% of the extracted zirconium will report to the high- activity waste (HAW) fraction using the 0.05 M H{sub 2}C{sub 2}O{sub 4} in 3.0 M HNO{sub 3} scrub, and greater than 99% of the extracted actinides are recovered with 0.001 M HEDPA.
Date: January 1, 1996
Creator: Brewer, K. N.; Herbst, R. S.; Law, J. D.; Garn, T. G.; Tillotson, R. D. & Todd, T. A.
open access

Additional nuclear criticality safety calculations for small-diameter containers

Description: This report documents additional criticality safety analysis calculations for small diameter containers, which were originally documented in Reference 1. The results in Reference 1 indicated that some of the small diameter containers did not meet the criteria established for criticality safety at the Portsmouth facility (K{sub eff} +2{sigma}<.95) when modeled under various contingency assumptions of reflection and moderation. The calculations performed in this report reexamine those cases which did not meet the criticality safety criteria. In some cases, unnecessary conservatism is removed, and in other cases mass or assay limits are established for use with the respective containers.
Date: January 1, 1996
Creator: Hone, M.J.
open access

Advanced gas turbine systems research. Quarterly report, October--December 1995

Description: This report summarizes the major accomplishments and reports issued by Advanced Gas Turbine Systems Research (AGTSR) during October 1, 1995 to December 31, 1995, reports on changes in the AGTSR membership, describes 1993, 1994 and 1995 subcontract progress, third combustion workshop, first combustion specialty meeting, materials workshop, industrial internship, research topics highlighted, and seminar sponsorship.
Date: January 1, 1996
open access

Advanced processing technology for high-efficiency, thin-film CuInSe₂ and CdTe solar cells. Final subcontract report, March 1, 1992--April 30, 1995

Description: This report describes work performed by the University of South Florida to develop a manufacturing-friendly fabrication process for CuInSe{sub 2} (CIS) solar cells. The process developed under this project uses conventional deposition processes and equipment, does not require stringent process control, and uses elemental Se as the selenium source. The authors believe it can be readily scaled up using off-the-shelf processing equipment and that it will meet the low manufacturing-cost objectives. Another significant achievement under this project was the development of a reactive sputtering deposition technology for ZnO. ZnO is used in many solar cell devices, and sputtering is a desirable manufacturing technology. The application of sputtering has been limited because conventional deposition uses ceramic targets that result in low sputtering rates. The use of Zn metal as the target in reactive sputtering overcomes this limitation. The authors have demonstrated that ZnO deposited by reactive sputtering has state-of-the-art opto-electronic properties. These developments result in large-area uniformity and optimized performance and provide a significant opportunity for applying and commercializing the technology. The second objective of this project was to fabricate high-efficiency CdTe solar cells using manufacturing-friendly processes. Three deposition processes were used to deposit CdS films: chemical bath deposition, rf sputtering, and close-spaced sublimation (CSS). The CdTe films were deposited by CSS. A cell with a record efficiency of 15.8% was obtained.
Date: January 1, 1996
Creator: Morel, D. L. & Ferekides, C. S.
open access

Advanced sulfur control concepts for hot gas desulfurization technology. Quarterly report, October--December 1995

Description: In the area of gas analysis, most of the attention during the past quarter was devoted to gaining an understanding of the operation of the Antek total sulfur analyzer, and making appropriate modifications in the unit. The primary problem is that the resistance of the capillary flow restrictor is not large enough, and the amount of sulfur which reaches the UV-analyzer results in the analyzer becoming saturated. We have added a N{sub 2} diluent flow downstream of the pyrotube tube which, we believe, will permit the unit to be operated at pressures to about 50 psig. Use of larger diluent flow rates to permit higher pressure operation is not feasible since larger diluent rates increase the back pressure on the quartz pyrotube (which operates at 1050{degrees}C) to unsafe levels. In the meantime, Antek is studying the redesign of the capillary flow restrictor to provide larger flow resistance. Studies on the regeneration of FeS in the atmospheric pressure reactor were almost completed during the quarter. Only a series of multicycle sulfidation-regeneration tests remains. The effects of reactive gas mol fraction and temperature have been examined using both O{sub 2}/N{sub 2} and H{sub 2}O/N{sub 2} atmospheres. The initial rate of regeneration was found to be a weak function of temperature and first-order in both O{sub 2} and H{sub 2}O concentration. In a test series in which the reactive gas contained both O{sub 2} and H{sub 2}O, the experimental initial rate was effectively equal to the sum of the individual initial rates, suggesting that the two reactions proceed independently of one another. Detailed correlation and statistical analysis of the data is currently being done. Principal effort during the quarter using the high pressure electrobalance was devoted to studying the regeneration of FeS in a H{sub 2}O/N{sub 2} atmosphere.
Date: January 1, 1996
open access

Advanced turbine systems program conceptual design and product development. Quarterly report, August--October 1995

Description: This report describes the tasks completed for the advanced turbine systems program. The topics of the report include last row turbine blade development, single crystal blade casting development, ceramic materials development, combustion cylinder flow mapping, shroud film cooling, directional solidified valve development, shrouded blade cooling, closed-loop steam cooling, active tip clearance control, flow visualization tests, combustion noise investigation, TBC field testing, catalytic combustion development, optical diagnostics probe development, serpentine channel cooling tests, brush seal development, high efficiency compressor design, advanced air sealing development, advanced coating development, single crystal blade development, Ni-based disc forging development, and steam cooling effects on materials.
Date: January 1, 1996
open access

Advanced wind turbine near-term product development. Final technical report

Description: In 1990 the US Department of Energy initiated the Advanced Wind Turbine (AWT) Program to assist the growth of a viable wind energy industry in the US. This program, which has been managed through the National Renewable Energy Laboratory (NREL) in Golden, Colorado, has been divided into three phases: (1) conceptual design studies, (2) near-term product development, and (3) next-generation product development. The goals of the second phase were to bring into production wind turbines which would meet the cost goal of $0.05 kWh at a site with a mean (Rayleigh) windspeed of 5.8 m/s (13 mph) and a vertical wind shear exponent of 0.14. These machines were to allow a US-based industry to compete domestically with other sources of energy and to provide internationally competitive products. Information is given in the report on design values of peak loads and of fatigue spectra and the results of the design process are summarized in a table. Measured response is compared with the results from mathematical modeling using the ADAMS code and is discussed. Detailed information is presented on the estimated costs of maintenance and on spare parts requirements. A failure modes and effects analysis was carried out and resulted in approximately 50 design changes including the identification of ten previously unidentified failure modes. The performance results of both prototypes are examined and adjusted for air density and for correlation between the anemometer site and the turbine location. The anticipated energy production at the reference site specified by NREL is used to calculate the final cost of energy using the formulas indicated in the Statement of Work. The value obtained is $0.0514/kWh in January 1994 dollars. 71 figs., 30 tabs.
Date: January 1, 1996
open access

Aerosol measurements from plasma torch cuts on stainless steel, carbon steel, and aluminum

Description: The main purpose of this project is to quantify aerosol particle size and generation rates produced by a plasma torch whencutting stainless steel, carbon steel and aluminum. the plasma torch is a common cutting tool used in the dismantling of nuclear facilities. Eventually, other cutting tools will be characterized and the information will be compiled in a user guide to aid in theplanning of both D&D and other cutting operations. The data will be taken from controlled laboratory experiments on uncontaminated metals and field samples taken during D&D operations at ANL nuclear facilities. The plasma torch data was collected from laboratory cutting tests conducted inside of a closed, filtered chamber. The particle size distributions were determined by isokinetically sampling the exhaust duct using a cascade impactor. Cuts on different thicknesses showed there was no observable dependence of the aerosol quantity produced as a function of material thickness for carbon steel. However, data for both stainless steel and aluminum revealed that the aerosol mass produced for these materials appear to have some dependance on thickness, with thinner materials producing tmore aerosols. The results of the laboratory cutting tests show that most measured particle size distributions are bimodal with one mode at about 0.2 {mu}m and the other at about 10 {mu}m. The average Mass Median Aerodynamic Diameters (MMAD`s) for these tests are 0.36 {+-}0.08 {mu}m for stainless steel, 0.48 {+-}0.17{mu}m for aluminum and 0.52{+-}0.12 {mu}m for carbon steel.
Date: January 1, 1996
Creator: Novick, V.J.; Brodrick, C.J.; Crawford, S.; Nasiatka, J.; Pierucci, K.; Reyes, V. et al.
open access

AFBC co-firing of coal and hospital waste. Quarterly progress report, February 1, 1995--April 30, 1995

Description: The project objective is to design, construct, install, provide operator training and start-up a circulating fluidized bed combustion system at the Lebanon Pennsylvania Veteran`s Affairs Medical Center. This unit will co-fire coal and hospital waste providing inexpensive and efficient destruction of both general and infectious hospital waste and steam generation. The steam generated is as follows: (1) Steam = 20,000 lb/hr, (2) Temperature = 353 F (saturated), (3) Pressure = 125 psig, and (4) Steam quality ={approximately}98.5%. On February 3, 1995 DONLEE notified Lebanon VA and DOE-METC that additional funding would be required to complete the project. This funding, in the amount of $1,140,127, is needed to complete the facility, start-up and shakedown the facility, perform the test program and write the final report. On March 7, 1995 the vendors were notified that the Lebanon VA Steam Plant Project was shut down and that all work outside DONLEE was stopped pending obtaining additional funding.
Date: January 1, 1996
Creator: Stuart, J. M.
open access

Aging assessment of surge protective devices in nuclear power plants

Description: An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.
Date: January 1996
Creator: Davis, J. F.; Subudhi, M. & Carroll, D. P.
open access

Alpha particle losses from Tokamak Fusion Test Reactor deuterium-tritium plasmas

Description: Because alpha particle losses can have a significant influence on tokamak reactor viability, the loss of deuterium-tritium alpha particles from the Tokamak Fusion Test Reactor (TFTR) has been measured under a wide range of conditions. In TFTR, first orbit loss and stochastic toroidal field ripple diffusion are always present. Other losses can arise due to magnetohydrodynamic instabilities or due to waves in the ion cyclotron range of frequencies. No alpha particle losses have yet been seen due to collective instabilities driven by alphas. Ion Bernstein waves can drive large losses of fast ions from TFTR, and details of those losses support one element of the alpha energy channeling scenario.
Date: January 1, 1996
Creator: Darrow, D. S.; Zweben, S. J. & Batha, S.
open access

Analysis/control of in-bed tube erosion phenomena in the fluidized bed combustion (FBC) system. Quarterly report

Description: This technical report summarizes the research work performed and progress achieved during the period of October 1, 1995 to December 31, 1995. A series of material wastage tests was carried out on cooled AISI 1018 steel and three thermal-sprayed coating specimens at an elevated environmental temperature (3000{degrees}C) using a nozzle type erosion tester. Test conditions simulated the erosion conditions at the in-bed tubes of fluidized combustors (FBCs). Angular silica quartz particles of average size 742 {micro}m were used for erodent particles for tests at an impact angle of 30{degrees}, at a particle velocity of 2.5 m/s for exposure periods up to 96 hours. The specimens were water-cooled on backside. Material wastage rates were determined from thickness loss measurements of specimens. Test results were compared with material wastage test results from testing isothermal specimens. The morphology of specimens was examined by scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS). It was found that the cooled specimens had greater material wastage than that of the isothermal specimens. The material wastage rate of cooling specimen for AISI 1018 was greater than that for thermal- sprayed coatings. The success in reduction of erosion wastage by cooled-coating specimens was related to the coatings, composition and morphology.
Date: January 1, 1996
Creator: Lee, Seong W.
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