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Hot helium flow test facility summary report

Description: This report summarizes the results of a study conducted to assess the feasibility and cost of modifying an existing circulator test facility (CTF) at General Atomic Company (GA). The CTF originally was built to test the Delmarva Power and Light Co. steam-driven circulator. This circulator, as modified, could provide a source of hot, pressurized helium for high-temperature gas-cooled reactor (HTGR) and gas-cooled fast breeder reactor (GCFR) component testing. To achieve this purpose, a high-temperature impeller would be installed on the existing machine. The projected range of tests which could be conducted for the project is also presented, along with corresponding cost considerations.
Date: June 1, 1980
Partner: UNT Libraries Government Documents Department
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Geothermal energy impact in Brazoria County. Final report, 15 July 1978-November 30, 1979

Description: All activities performed by Alvin Community College and the University of Texas at Austin in association with the development of Geopressured-Geothermal energy are contained in this report. A discussion of the progress of the Test Well is also contained herein. Public seminars and workshops were presented to the local community. A summer institute in energy was also presented to local public school teachers. A compaign to publicize the development of the new energy resource was also waged. An overall evaluation of the project is also attached.
Date: June 1, 1980
Creator: Horine, B.
Partner: UNT Libraries Government Documents Department
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850/sup 0/C VHTR plant technical description

Description: This report describes the conceptual design of an 842-MW(t) process heat very high temperature reactor (VHTR) plant having a core outlet temperature of 850/sup 0/C (1562/sup 0/F). The reactor is a variation of the high-temperature gas-cooled reactor (HTGR) power plant concept. The report includes a description of the nuclear heat source (NHS) and of the balance of reactor plant (BORP) requirements. The design of the associated chemical process plant is not covered in this report. The reactor design is similar to a previously reported VHTR design having a 950/sup 0/C (1742/sup 0/F) core outlet temperature.
Date: June 1, 1980
Partner: UNT Libraries Government Documents Department
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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels With Dilute Aqua Regia

Description: The Darex process developed for ihe recovery of U from stainless steel- containing reactor fuels consists of dissolution of the fuel material in dilute aqua regia, removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and adjustment of the nitrate solution to solvent extraction feed conditions. Each step can be either continuous, semi-continuous, or batch with continuous operation showing much higher throughput for comparable equipment. The preferred dissolvent is 5 M HNO/ sub 3/-2 M HCl, since dissolution rates and metal loadings are near maximum. Nitric acid from 60 to 95 wt% can be used in decreasing ihe chloride concentration to <350 ppm; ihe higher strength acids have process advantages. Excess nitric acid is recovered and recycled during produciion of a concentrated metal-salt solution, which is diluted io Purex solvent extraction feed acidity, 2- 3 M HNO/sub 3/. Titanium is a satisfactory material of construction, wiih corrosion rates <l mil/mo in all process environments and over-all heat transfer coefficients comparable to those of stainless steel. (auth)
Date: June 1, 1962
Creator: Kitts, F.G. & Clark, W.E.
Partner: UNT Libraries Government Documents Department
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Fuel performance annual report for 1989

Description: This annual report, the twelfth in a series, provides a brief description of fuel performance during 1989 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related US Nuclear Regulatory Commission evaluations are included.
Date: June 1, 1992
Creator: Bailey, W.J.; Berting, F.M. (Pacific Northwest Lab., Richland, WA (United States)) & Wu, S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology)
Partner: UNT Libraries Government Documents Department
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Compressed air energy storage (CAES) environmental control concerns and program plan

Description: This report assesses the required environmental research and recommends a program plan to assist DOD's Environmental Control Technology Division (ECT) in performing its mission of ensuring that the procedures, processes, systems, and strategies necessary to minimize any adverse environmental impacts of compressed air energy storage (CAES) are developed in a timely manner so as not to delay implementation of the technology. To do so, CAES technology and the expected major environmental concerns of the technology are described. Second, ongoing or planned research in related programs and the applicability of results from these programs to CAES environmental research are discussed. Third, the additional research and development required to provide the necessary environmental data base and resolve concerns in CAES are outlined. Finally, a program plan to carry out this research and development effort is presented.
Date: June 1, 1980
Creator: Beckwith, M.A. & Boehm, D.W.
Partner: UNT Libraries Government Documents Department
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Blast Loading and Response of Underground Concrete-Arch Protective Structures

Description: Four reinforced-concrete arch structures, with the top of arch crown 4 ft below ground surface, were exposed at high overpressure ranges from Priscilla Burst in order to obtain data on their resistance to blast, radiation, and missile hazards. The four structures received actual air overpressures of 56, 124, and 199 psi and suffered only minor damage, all remaining structurally serviceable. The entranceway used for the structures sealed out the air pressure. It was not designed to attenuate radiation and thus did not provide adequate radiation protection for personnel. There were no missile and apparently no dust hazards in any of the structures. Results of the test indicate that an underground reinforced-concrete arch is an excellent structural shape for resisting the effects of a kiloton-range air burst. (C.H.)
Date: June 1, 1959
Creator: Flathau, W.J.; Breckenridge, R.A. & Wiehle, C.K.
Partner: UNT Libraries Government Documents Department
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Cadmium sulfide/copper sulfide heterojunction cell research. Final report, February 26, 1979-July 15, 1980

Description: Extensive modifications were made to the multi-source deposition apparatus. These include the installation of a larger vacuum chamber on the existing system. The new chamber provides improved inter-source shielding, an improved substrate mounting and heating system, and a vacuum interlock for introducing substrates. CdS resistivity control by both In doping and off-stoichiometric deposition has been investigated. Indium doping has been achieved both by diffusion from a pre-deposited In layer and by using In doped sputtering targets. Resistivities in the range 0.1 to 5 ..cap omega..-cm have been obtained for target doping levels of from 0.1 to 1 at. percent of In. These resistivities were found to be critically dependent on the H/sub 2/S injection rate, apparently because of compensation by Cd vacancies. Off-stoichiometry CdS coatings with solar-illuminated resistivities of about 10/sup 2/ ..cap omega..-cm have been deposited, using a cyclic reactive sputtering process were the H/sub 2/S injection is periodically switched on and off. The Cu/sub x/S deposition process was found to be sensitive to the period of cathode operation prior to coating deposition, probably because of the conditioning of cathode and shield surfaces. All-sputter-deposited Cd(Zn)S/Cu/sub 2/S cells, with Cd(Zn)S layers deposited using a Cd-0.10 Zn target doped with 2 atomic percent In, have yielded efficiencies of approx. 0.4%. All-sputtered cells with efficiencies of approx. 0.6% have been fabricated, using undoped CdS deposited by the pulse injection process. Efficiencies of approx. 1.2% have been achieved for cells with undoped sputter-deposited CdS and CuCl dry processed Cu/sub 2/S.
Date: June 30, 1980
Creator: Thornton, J. A. & Cornog, D. G.
Partner: UNT Libraries Government Documents Department
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SLAC linear collider conceptual design report

Description: The linear collider system is described in detail, including the transport system, the collider lattice, final focusing system, positron production, beam damping and compression, high current electron source, instrumentation and control, and the beam luminosity. The experimental facilities and the experimental uses are discussed along with the construction schedule and estimated costs. Appendices include a discussion of space charge effects in the linear accelerator, emittance growth in the collider, the final focus system, beam-beam instabilities and pinch effects, and detector backgrounds. (GHT)
Date: June 1, 1980
Partner: UNT Libraries Government Documents Department
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State legislatures and energy policy in the Northeast: energy facility siting and legislative action

Description: At the Federal level, a vast array of bureaucratic and legislative institutions are presently immersed in various explorations of energy policy and its national ramifications. Almost each of the 50 states has Energy offices. One element of the institutional/political equation, however, often is missed in studies of energy policy: the state legislature. This institution may well be vitally important to formulation of broad policies, and certainly is critical to successful implementation of certain aspects of those policies--especially when new enabling legislation, new tax incentives, or new regulatory powers are required. The study covers three main aspects of energy-policy formulation and action by state legislatures: legislative structure; enactment of energy-facility-siting laws; and passage (or defeat) of significant energy legislation of a more general nature. Emphasis is placed on energy-facility-siting statutes and approaches for two reasons. First, energy facilities have a great impact on land use, environmental quality, and economic growth. Second, siting of these facilities raises inherent conflicts in the attempt to achieve balance between potentially contradictory objectives. The states of New Jersey and Maryland were examined in considerable depth as examples in this study. (MCW)
Date: June 1, 1977
Partner: UNT Libraries Government Documents Department
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Photovoltaic engineering services pertinent to solar energy conversion

Description: The application of the compound parabolic concentrator (CPC) for use with solar cells has been investigated. Experiments with state-of-the-art Si cells in a CPC and under solar concentration were performed. A theoretical model for calculating the behavior of Si solar cells with concentration was developed. Detailed calculations of the energy distribution in the CPC were made. Finally a cost effectiveness analysis shows that the CPC system will produce power at very much lower cost than will flat panel solar cell arrays. (auth)
Date: June 1, 1975
Creator: Bell, R O; Ho, J C.T.; Kurth, W & Surek, T
Partner: UNT Libraries Government Documents Department
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PATHFINDER ATOMIC POWER PLANT STEAM SEPARATOR DEVELOPMENT

Description: Development of a steam separator the Pathfinder Reactor is reported. A full-scale separator model was developed through the combination of scale-model testing and the application of principles associated with the existing theory of centrifugal separation. This model was put through full-scale air-water tests which led to modifications and a final design which meets Pathfinder requirements. Design data are included for the reactor and the steam separator. (J.R.D.)
Date: June 15, 1962
Creator: Kutsch, G. C.; Swanson, D. H. & Yant, H. W.
Partner: UNT Libraries Government Documents Department
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Fast-neutron total and scattering cross sections of elemental palladium

Description: Neutron total cross sections of palladium are measured from approx. = 0.6 to 4.5 MeV with resolutions of approx. = 30 to 70 keV at intervals of less than or equal to 50 keV. Differential neutron elastic- and inelastic-scattering cross sections are measured from 1.4 to 3.85 MeV at intervals of 50 to 100 keV and at 10 to 20 scattering angles distributed between approx. = 20 and 160/sup 0/. The experimental results are compared with respective quantities given in ENDF/B-V and used to deduce an optical potential that provides a good description of the measured values.
Date: June 1, 1982
Creator: Smith, A. B.; Guenther, P. T. & Whalen, J. F.
Partner: UNT Libraries Government Documents Department
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WONDY V: a one-dimensional finite-difference wave-propagation code

Description: WONDY V solves the finite difference analogs to the Lagrangian equations of motion in one spatial dimension (planar, cylindrical, or spherical). Simulations of explosive detonation, energy deposition, plate impact, and dynamic fracture are possible, using a variety of existing material models. In addition, WONDY has proven to be a powerful tool in the evaluation of new constitutive models. A preprocessor is available to allocate storage arrays commensurate with problem size, and automatic rezoning may be employed to improve resolution. This document provides a description of the equations solved, available material models, operating instructions, and sample problems.
Date: June 1, 1982
Creator: Kipp, M.E. & Lawrence, R.J.
Partner: UNT Libraries Government Documents Department
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Energy dependence of metallic-encapsulated thermoluminescent dosimeters. Annual report

Description: The gamma-ray energy responses of encapsulated /sup 7/LiF and CaF/sub 2/:Mn thermoluminescent dosimeters were measured and compred to calculated values. This study was performed in order to improve the accuracy of gamma-ray heating measurements made in polyenergetic gamma-ray fields such as Argonne National Laboratory's Zero Power Reactors. Equations used in the development of the TERC/III computer code and code input parameters are specified. A section on TLD precision is also included. Comparisons between calculations and experiments are reported for a gamma-ray energy range of 0.122 to 1.33 MeV and encasement media with a range of atomic numbers from 13 to 82.
Date: June 1980
Creator: Simons, G. G.
Partner: UNT Libraries Government Documents Department
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The International Coal Statistics Data Base program maintenance guide

Description: The International Coal Statistics Data Base (ICSD) is a microcomputer-based system which contains information related to international coal trade. This includes coal production, consumption, imports and exports information. The ICSD is a secondary data base, meaning that information contained therein is derived entirely from other primary sources. It uses dBase III+ and Lotus 1-2-3 to locate, report and display data. The system is used for analysis in preparing the Annual Prospects for World Coal Trade (DOE/EIA-0363) publication. The ICSD system is menu driven and also permits the user who is familiar with dBase and Lotus operations to leave the menu structure to perform independent queries. Documentation for the ICSD consists of three manuals -- the User's Guide, the Operations Manual, and the Program Maintenance Manual. This Program Maintenance Manual provides the information necessary to maintain and update the ICSD system. Two major types of program maintenance documentation are presented in this manual. The first is the source code for the dBase III+ routines and related non-dBase programs used in operating the ICSD. The second is listings of the major component database field structures. A third important consideration for dBase programming, the structure of index files, is presented in the listing of source code for the index maintenance program. 1 fig.
Date: June 1, 1991
Partner: UNT Libraries Government Documents Department
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Resource, technology, and environment at the geysers

Description: A general review, description, and history of geothermal development at the Geysers is presented. Particular emphasis is placed on environmental impacts of development of the area. The discussion is presented under the following chapter titles: introduction; energy, enthalpy and the First Law; vapor-producing geothermal reservoirs--review and models; geothermal; entropy and the Second Law; power plants--basics; H/sub 2/S emissions; hydrogen sulfide--possible health effects and odor; other emissions; power plant hydrogen sulfide abatement; hot water based geothermal development; phytotoxicity of geothermal emissions; appendices; and bibliography. (JGB)
Date: June 1, 1977
Creator: Weres, O.; Tsao, K. & Wood, B.
Partner: UNT Libraries Government Documents Department
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Cross flow filter for AEPSC: TIDD slipstream HGCU project preliminary design package for Westinghouse cross flow filter system

Description: The Westinghouse ceramic cross-flow filter element is constructed of multiple layers of thin, porous ceramic plates that contain ribs to form gas flow channels. Consecutive layers of the ceramic plates are oriented such that the channels of alternating plates are at an angle of 90 degrees ( cross flow'') to each other. The current size of a ceramic cross flow filter element is 12 in. {times} 12 in. {times} 14 in. Both sides of the short channels (4 in.) are exposed to the particle-laden coal gas. One end of the long (12 in.) channels is sealed while the other end of the long channel is mounted to the clean gas plenum. The particle-laden coal gas flows through the roof and floor'' of the porous ceramic plates that comprise the short, dirty side'' channels. The gas flows through the porous plates to the long, clean side'' channels. The gas flows through the porous plates to the long, clean side'' channels and finally to the clean gas plenum. The dust cake on the dirty side'' channels is periodically removed by applying a high-pressure reverse pulse of dry, clean gas through the clean gas plenum. For the TIDD plant filter slipstream, air will be utilized for filter cleaning.
Date: June 16, 1989
Creator: Haldipur, G.B. & Lippert, T.E.
Partner: UNT Libraries Government Documents Department
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General Reactor Sizing Techniques. Volume I. Aerothermodynamic Optimization

Description: A method is presented for the aerothermodynamic optimization of the net power and/or propulsive thrust per unit reactor free flow area of a nuclear power plant operating on the Brayton cycle. A system so optimized will translate into the minimum size, therefore the minimum weight, nuclear system for any selection of reactor materials, lifetime, and fuel loading. The theory and development of the thermodynamic optimization process, the importance and effect of various parameters, and specific methods to be employed in the optimization of the various forms of the Brayton cycle are discussed. A sample calculation for the case of the ramjet application is included. The results of the application of these techniques to any Brayton cycle system may be used in conjunction with nuclear sizing methods, for beryllia-moderated reactors, to determine the required reactor size as a function of fuel loading and reactivity requirements. (auth)
Date: June 1, 1961
Creator: Prickett, W.Z.
Partner: UNT Libraries Government Documents Department
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Indium phosphide/cadmium sulfide thin-film solar cells. Quarterly technical progress report No. 3, December 1979-April 1980

Description: Thin films (approx. 1 ..mu..m thick) and large grains (approx. 40 x 40 ..mu..m) of InP were epitaxially deposited on low-cost recrystallized CdS (RXCdS) substrates at 280/sup 0/C by planar reactive deposition. At 380/sup 0/C, a 0.4- to 1.0-..mu..m-thick In-Cd-S transition layer between the InP and the RXCdS degrades the quality of the InP epitaxy. However, p-type InP films were prepared at this temperature by Be-doping and capping the entire RXCdS substrate with InP. Large grains of CdTe (approx. 40 ..mu..m) were also deposited on RXCdS substrates at 460/sup 0/C by physical vapor deposition. The grain size of the RXCdS is typically 40 ..mu..m. However, during this period we prepared RXCdS with grains having dimensions up to 300 ..mu..m.
Date: June 1, 1980
Creator: Zanio, K.
Partner: UNT Libraries Government Documents Department
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