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Advanced development of electrical-energy-storage components for high-reliability applications (open access)

Advanced development of electrical-energy-storage components for high-reliability applications

This program was undertaken in order to study the following: (1) design and fabrication of prototype test capacitors; (2) dc partial discharge analysis; (3) repetitive charge-discharge life testing; (4) theoretical and experimental analysis; and (5) computer modeling. A brief overview of each of these program elements is presented. (MOW)
Date: 1981
Creator: Bickford, K. J.; Mauldin, G. H. & Sargeant, W. J.
Object Type: Article
System: The UNT Digital Library
Advanced Fuel Cell Development Progress Report: January-March 1981 (open access)

Advanced Fuel Cell Development Progress Report: January-March 1981

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) developing alternative concepts for components for molten carbonate fuel cells and (2) improving our understanding of component behavior.
Date: October 1981
Creator: Dusek, J. T.; Pierce, R. D. & Arons, R. M.
Object Type: Report
System: The UNT Digital Library
Advanced Fuel Cell Development Progress Report: July-September 1980 (open access)

Advanced Fuel Cell Development Progress Report: July-September 1980

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) investigating alternative concepts for components of molten carbonate fuel cell stacks and (2) improving our understanding of component behavior.
Date: July 1981
Creator: Pierce, R. D.; Arons, R. M.; Dusek, J. T.; Fraioli, A. V.; Kucera, G. H.; Poeppel, R. B. et al.
Object Type: Report
System: The UNT Digital Library
Advanced fuel concepts and applications (open access)

Advanced fuel concepts and applications

Despite their more stringent plasma heating and confinement requirements, advanced fuel (AF) fusion cycles potentially offer improved environmental compatibility and lower costs. This comes about by elimination of tritium breeding requirements and by a reduction in neutron flux (hence, activation and radiation damage). Also a larger energy fraction carried by charged particles makes direct energy conversion more suitable. As a first application, a symbiotic system of semi-catalyzed-deuterium fueled hybrid fuel factories, supplying both fissle fuel to light water reactors and /sup 3/He to D-/sup 3/He satellite fusion reactors, is proposed. Subsequently, an evolution into a system of synfuel factories with satellite D-/sup 3/He reactors is envisioned.
Date: January 1, 1981
Creator: Miley, George H.
Object Type: Article
System: The UNT Digital Library
Advanced-fuel reversed-field pinch reactor (RFPR) (open access)

Advanced-fuel reversed-field pinch reactor (RFPR)

The utilization of deuterium-based fuels offers the potential advantages of greater flexibility in blanket design, significantly reduced tritium inventory, potential reduction in radioactivity level, and utilization of an inexhaustible fuel supply. The conventional DT-fueled Reversed-Field Pinch Reactor (RFPR) designs are reviewed, and the recent extension of these devices to advanced-fuel (catalyzed-DD) operation is presented. Attractive and economically competitive DD/RFPR systems are identified having power densities and plasma parameters comparable to the DT systems. Converting an RFP reactor from DT to DD primarily requires increasing the magnetic field levels a factor of two, still requiring only modest magnet coil fields (less than or equal to 4 T). When compared to the mainline tokamak, the unique advantages of the RFP (e.g., high beta, low fields at the coils, high ohmic-heating power densities, unrestricted aspect ratio) are particularly apparent for the utilization of advanced fuels.
Date: October 1, 1981
Creator: Hagenson, Randy L. & Krakowski, Robert A.
Object Type: Article
System: The UNT Digital Library
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report for Period October 1, 1980-December 31, 1980. (open access)

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report for Period October 1, 1980-December 31, 1980.

This report presents the results of work performed from October 1, 1980 through December 31, 1980 on the Advanced Gas- Cooled Nuclear Reactor Materials Evaluation and Development Program.
Date: February 15, 1981
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced international training course on state systems of accounting for and control of nuclear materials (open access)

Advanced international training course on state systems of accounting for and control of nuclear materials

This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.
Date: October 1, 1981
Creator: unknown
Object Type: Article
System: The UNT Digital Library
Advanced Pressurized Water Reactor for Improved Resource Utilization: Part I - Survey of Potential Improvements (open access)

Advanced Pressurized Water Reactor for Improved Resource Utilization: Part I - Survey of Potential Improvements

This document is an interim report under ACDA BOA AC9NX707, Task Order 80-03, which covers the evaluation of certain potential improvements in pressurized water reactor designs intended to enhance uranium fuel utilization. The objective of these evaluations is to seek advanced, non-retrofittable improvements that could possibly be commercialized by the end of the century, and, on the basis of a preliminary evaluation, to select compatible improvements for incorporation into a composite advanced pressurized water reactor concept. The principal areas of investigation include reduced parasitic absorption of neutrons (Task 1), reduced neutron leakage (Task 2), and alternative fuel design concepts (Task 3). To the extent possible, the advanced concept developed in an earlier study (Retrofittable Modifications to Pressurized Water Reactors for Improved Resource Utilization, SSA-128, October 1980) is used as a basis in developing the advanced composite concept. The reference design considered typical of present PWR commercial practice is the system described in RESAR-414, Reference Safety Analysis Report, Westinghouse Nuclear Energy Systems, October 1976.
Date: September 15, 1981
Creator: Turner, S. E.; Gurley, M. K.; Kirby, K. D. & Mitchell, W., III
Object Type: Report
System: The UNT Digital Library
Advanced pressurized water reactor for improved resource utilization, part II - composite advanced PWR concept (open access)

Advanced pressurized water reactor for improved resource utilization, part II - composite advanced PWR concept

This report evaluates the enhanced resource utilization in an advanced pressurized water reactor (PWR) concept using a composite of selected improvements identified in a companion study. The selected improvements were in the areas of reduced loss of neutrons to control poisons, reduced loss of neutrons in leakage from the core, and improved blanket/reflector concepts. These improvements were incorporated into a single composite advanced PWR. A preliminary assessment of resource requirements and costs and impact on safety are presented.
Date: September 15, 1981
Creator: Turner, S. E.; Gurley, M. K.; Kirby, K. D. & Mitchell, W., III
Object Type: Report
System: The UNT Digital Library
Advanced pulverized coal combustor for control of NO/sub x/ emissions. First quarterly report, September 24-December 24, 1980 (open access)

Advanced pulverized coal combustor for control of NO/sub x/ emissions. First quarterly report, September 24-December 24, 1980

The first quarter results under the Advanced Pulverized Coal Combustor for Control of NO/sub x/ Emissions Program (DOE Contract DE-AC22-80PC30296) are reported. A preliminary gas phase reaction model for predicting fuel NO/sub x/ formation during combustion of methane fuel has been constructed. Predictions of NO/sub x/ formation under stirred reactor conditions agree with existing experimental data. Thermal NO/sub x/ and coal reaction data will be developed and verified during the next reporting period. Progress has been made in formulating the changes necessary to upgrade the Acurex PROF code for use as the comprehensive data analysis tool in this program. The radiation modeling and the incorporation of the needed modifications into the PROF code will occur during the next reporting period. The idealized combustor was designed, and requests for bids to fabricate the combustor were submitted. Combustor fabrication will be completed during the next reporting period.
Date: January 30, 1981
Creator: Pam, R.; Chu, E. K. & Kelly, J. T.
Object Type: Report
System: The UNT Digital Library
Advanced pulverized-coal combustor for control of NO/sub x/ emissions. Second quarterly report, December 25, 1980-April 3, 1981 (open access)

Advanced pulverized-coal combustor for control of NO/sub x/ emissions. Second quarterly report, December 25, 1980-April 3, 1981

Second quarter results under the Advanced Pulverized Coal Combustor for Control of NO/sub x/ Emissions Program are reported. The program uses an idealized one-dimensional combustor, incorporating fuel staging. A comprehensive computer model is being developed under the program to allow NO mechanisms and rates to be extracted from the experimental data. During the quarter, modification of the existing PROF code to include particle effects was begun. Various aspects of the solution procedure are described in this report. Refinements in the kinetic thermochemical data are completed, providing satisfactory agreement between calculated NO predictions and selected experimental data. Combustor mechanical design was described last quarter. The heat transfer analysis used in the design of the combustor is reported herein. Initial combustion tests will be run next quarter.
Date: January 1, 1981
Creator: Pam, R. L.; Suttmann, S. T.; Kelly, J. T. & Chu, E. K.
Object Type: Report
System: The UNT Digital Library
Advanced reactor design study. Assessing nonbackfittable concepts for improving uranium utilization in light water reactors (open access)

Advanced reactor design study. Assessing nonbackfittable concepts for improving uranium utilization in light water reactors

The objective of the Advanced Reactor Design Study (ARDS) is to identify and evaluate nonbackfittable concepts for improving uranium utilization in light water reactors (LWRs). The results of this study provide a basis for selecting and demonstrating specific nonbackfittable concepts that have good potential for implementation. Lead responsibility for managing the study was assigned to the Pacific Northwest Laboratory (PNL). Nonbackfittable concepts for improving uranium utilization in LWRs on the once-through fuel cycle were selected separately for PWRs and BWRs due to basic differences in the way specific concepts apply to those plants. Nonbackfittable concepts are those that are too costly to incorporate in existing plants, and thus, could only be economically incorporated in new reactor designs or plants in very early stages of construction. Essential results of the Advanced Reactor Design Study are summarized.
Date: September 1, 1981
Creator: Fleischman, R. M.; Goldsmith, S.; Newman, D. F.; Trapp, T. J. & Spinrad, B. I.
Object Type: Report
System: The UNT Digital Library
Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981 (open access)

Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981

This is the fourth combined quarterly progress report for those projects that are part of the Advanced Research and Technology Development Fossil Energy Materials Program. The objective is to conduct a program of research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Work performed on the program generally falls into the Applied Research and Exploratory Development categories as defined in the DOE Technology Base Review, although basic research and engineering development are also conducted. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating cntractor organizations. All subcontractor work is monitored by Program staff members at ORNL and Argonne National Laboratory. This report is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1981 in which projects are organized according to fossil energy technologies. We hope this series of AR and TD Fossil …
Date: December 1, 1981
Creator: Bradley, R.A. (comp.)
Object Type: Report
System: The UNT Digital Library
Advanced research and technology, direct utilization: recovery of minerals from coal fly ash. Fossil energy program. Technical progress report, 1 October 1980-31 December 1980 (open access)

Advanced research and technology, direct utilization: recovery of minerals from coal fly ash. Fossil energy program. Technical progress report, 1 October 1980-31 December 1980

The purpose of this research is to develop methods to process fly ash for the separation and use of an iron-rich fraction, for the recovery of metals, primarily Al and Ti, and for use of the process residues. Research during this report period of the HiChlor process for the extraction of alumina and titania by high-temperature chlorination of a fly ash-reductant mixture included investigation of the simulation of the reactions as a design tool, the assembly of a unit to measure reaction kinetic rates and particle specific surface areas and porosities, and the design of equipment to measure necessary chloride product separation data. A pretreatment chlorination reaction using CO and Cl/sub 2/ was found to be capable of removing 80% of the iron with only minimal alumina and silica reaction. Development of the lime-soda sinter process includes the collection of data on the phenomenon of auto-disintegration of lime-fly ash sinters. Results indicate that it is the presence of minor constituents having +5 pr +6 valence cations of a size that can enter the lattice of the calcium silicate which prevent sinter auto-disintegration.
Date: February 1, 1981
Creator: Burnet, G.; Weiss, S. J. & Murtha, M. J.
Object Type: Report
System: The UNT Digital Library
Advanced Selenide Thermoelectric Development Program. Final Report (open access)

Advanced Selenide Thermoelectric Development Program. Final Report

The primary objective of this work was to demonstrate that copper silver selenide and TAGS could be segmented. The hot junction temperature was planned to be 725/sup 0/C with the segmentation temperature at 400/sup 0/C, both temperatures were selected to prevent excessive sublimation from the hot ends of the segments, respectively. The program was planned as a cooperative effort between General Atomic company and Teledyne Energy Systems. Accordingly, General Atomic synthesized the CuAgSe that was used to fabricate the test hardware that was ultimately delivered to General Atomic for testing. Both the CuAgSe and TAGS were hot pressed in an argon atmosphere then the segments were furnace-bonded to each other. A secondary objective was to produce CuAgSe powder by rapid solidification.
Date: July 20, 1981
Creator: Seetoo, W. R.
Object Type: Report
System: The UNT Digital Library
Advanced Test Accelerator (ATA) pulse power technology development (open access)

Advanced Test Accelerator (ATA) pulse power technology development

The Advanced Test Accelerator (ATA) is a pulsed linear induction accelerator with the following design parameters: 50 MeV, 10 kA, 70 ns, and 1 kHz in a ten-pulse burst. Acceleration is accomplished by means of 190 ferrite-loaded cells, each capable of maintaining a 250 kV voltage pulse for 70 ns across a 1-inch gap. The unique characteristic of this machine is its 1 kHz burst mode capability at very high currents. This paper dscribes the pulse power development program which used the Experimental Test Accelerator (ETA) technology as a starting base. Considerable changes have been made both electrically and mechanically in the pulse power components with special consideration being given to the design to achieve higher reliability. A prototype module which incorporates all the pulse power components has been built and tested for millions of shots. Prototype components and test results are described.
Date: March 9, 1981
Creator: Reginato, L.L.; Branum, D. & Cook, E.
Object Type: Article
System: The UNT Digital Library
Advanced thermionic technology program. Progress report No. 47, April, May, June 1981 (open access)

Advanced thermionic technology program. Progress report No. 47, April, May, June 1981

The primary long-term goal is to improve thermionic performance to the level that thermionic topping of fossil-fuel powerplants becomes technically possible and economically attractive. An intermediate goal is to operate a thermionic module in a power plant during the mid-1980's. A short-term goal is to demonstrate reliable thermionic operation in a combustion environment. Progress made during the three-month period from April through June 1981 is reported. During this period, significant accomplishments include: (1) continuing stable output from the combustion test of the one-inch diameter hemispherical silicon carbide diode (Converter No. 239) at an emitter temperature of 1730 K for a period of over 8500 hours; (2) determination of the elemental composition (i.e., molybdenum, nickel and cesium) through the sublimed molybdenum collector of Converter No. 262; and (3) demonstration of tungsten CVD onto molybdenum flange using a reuseable graphite mandrel.
Date: January 1, 1981
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced thermochemical hydrogen cycles (open access)

Advanced thermochemical hydrogen cycles

The overall objective of this program is to contribute to the development of practical thermochemical cycles for the production of hydrogen from water. Specific goals are: investigate and evaluate the technical and economic viability of thermochemical cycles as an advanced technology for producing hydrogen from water; investigate and evaluate the engineering principles involved in interfacing individual thermochemical cycles with the different thermal energy sources (high temperature fission, solar, and fusion); and conduct a continuing research and development effort to evaluate the use of solid sulfates, oxides and other compounds as potentially advanced cycles and as alternates to H/sub 2/SO/sub 4/ based cycles. Basic thermochemistry studies have been completed for two different steps in the decomposition of bismuth sulfate. Two different bismuth sulfate cycles have been defined for different sulfuric acid strengths. The eventual best cycle will depend on energy required to form sulfuric acid at different concentrations. A solids decomposition facility has been constructed and practical studies of solid decompositions are being conducted. The facility includes a rotary kiln system and a dual-particle fluidized bed system. Evaluation of different types of cycles for coupling with different heat sources is continuing.
Date: January 1, 1981
Creator: Hollabaugh, C.M. & Bowman, M.G.
Object Type: Article
System: The UNT Digital Library
Advances in automated noise data acquisition and noise source modeling for power reactors (open access)

Advances in automated noise data acquisition and noise source modeling for power reactors

A newly expanded program, directed toward achieving a better appreciation of both the strengths and limitations of on-line, noise-based, long-term surveillance programs for nuclear reactors, is described. Initial results in the complementary experimental (acquisition and automated screening of noise signatures) and theoretical (stochastic modeling of likely noise sources) areas of investigation are given.
Date: January 1, 1981
Creator: Clapp, N. E., Jr.; Kryter, R. C.; Sweeney, F. J. & Renier, J. A.
Object Type: Article
System: The UNT Digital Library
Advances in optical materials for large aperture lasers (open access)

Advances in optical materials for large aperture lasers

Lawrence Livermore National Laboratory (LLNL) is using large aperture Nd: glass lasers to investigate the feasibility of inertial confinement fusion. In our experiments high power laser light is focussed onto a small (100 to 500 micron) target containing a deuterium-tritium fuel mixture. During the short (1 to 5 ns) laser pulse the fuel is compressed and heated, resulting in fusion reactions. The generation and control of the powerful laser pulses for these experiments is a challenging scientific and engineering task, which requires the development of new optical materials, fabrication techniques, and coatings. LLNL with the considerable cooperation and support from the optical industry, where most of the research and development and almost all the manufacturing is done, has successfully applied several new developments in these areas.
Date: December 15, 1981
Creator: Stokowski, S. E.; Lowdermilk, W. H.; Marchi, F. T.; Swain, J. E.; Wallerstein, E. P. & Wirtenson, G. R.
Object Type: Article
System: The UNT Digital Library
Advisory Council for Technical-Vocational Education in Texas Annual Report: 1980 (open access)

Advisory Council for Technical-Vocational Education in Texas Annual Report: 1980

Annual report of the Advisory Council for Technical-Vocational Education in Texas describing goals, activities, and accomplishments during fiscal year 1980.
Date: 1981
Creator: Advisory Council for Technical-Vocational Education in Texas
Object Type: Report
System: The Portal to Texas History
Advisory Council for Technical-Vocational Education in Texas Annual Report: 1981 (open access)

Advisory Council for Technical-Vocational Education in Texas Annual Report: 1981

Annual report of the Advisory Council for Technical-Vocational Education in Texas describing goals, activities, and accomplishments during fiscal year 1981.
Date: December 1, 1981
Creator: Advisory Council for Technical-Vocational Education in Texas
Object Type: Report
System: The Portal to Texas History
Aeorsol Characterization from a Simulated HCDA (open access)

Aeorsol Characterization from a Simulated HCDA

Environmental conditions simulating the HCDA on a reduced scale provided the following information: Aerosols resulting from the condensation of gaseous constituents without sodium generally comprise small, spherical particles (diameter 0.01 to 0.25 um) and branched chain-like structures. Aerosols resulting from the condensation of gaseous constituents with sodium generally comprise spherical, small (diameter 0.01 to 0.50 um) particles, with some branched chain-like structures and some agglomerating particles. Electron diffraction analyses identified actinide dioxides, the constituents of stainless steel, an oxide of sodium (Na2O), sodium uranates (Na3UO4 and Na4UO5), and a sodium plutonate compound (Na4PuO5). Initial solubility studies indicated that 12.1% of the plutonium-239 dissolved in distilled water when a mixed-oxide (Pu, U) stainless steel pellet was vaporized with sodium. Reaction products are controlled kinetically during cooling rather than by equilibrium thermodynamics.
Date: June 1, 1981
Creator: Zanotelli, W. A.; Miller, G. D. & Johnson, E. W.
Object Type: Report
System: The UNT Digital Library
Aerial Gamma Ray and Magnetic Survey, Andalusia Quadrangle, Alabama: Final Report (open access)

Aerial Gamma Ray and Magnetic Survey, Andalusia Quadrangle, Alabama: Final Report

A report regarding an aerial gamma-ray and magnetic survey of the Andalusia Quadrangle, Alabama
Date: April 1981
Creator: unknown
Object Type: Report
System: The UNT Digital Library