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Hot helium flow test facility summary report
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
Creator:
unknown
System:
The UNT Digital Library
Geothermal energy impact in Brazoria County. Final report, 15 July 1978-November 30, 1979
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.
System:
The UNT Digital Library
850/sup 0/C VHTR plant technical 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
Creator:
unknown
System:
The UNT Digital Library
Fuel performance annual report for 1989
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)
System:
The UNT Digital Library
SLAC linear collider conceptual design report
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
Creator:
unknown
System:
The UNT Digital Library
State legislatures and energy policy in the Northeast: energy facility siting and legislative action
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
Creator:
unknown
System:
The UNT Digital Library
Photovoltaic engineering services pertinent to solar energy conversion
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
System:
The UNT Digital Library
Fast-neutron total and scattering cross sections of elemental palladium
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.
System:
The UNT Digital Library
The International Coal Statistics Data Base program maintenance guide
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 …
Date:
June 1, 1991
Creator:
unknown
System:
The UNT Digital Library
Resource, technology, and environment at the geysers
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.
System:
The UNT Digital Library
Project R. D. Bailey experimental excavation program. [Spillway]
None
Date:
June 1, 1975
Creator:
Bechtell, W.R.
System:
The UNT Digital Library
Development of enhanced heat transfer/transport/storage slurries for thermal-system improvement
None
Date:
June 1, 1982
Creator:
Kasza, K. E. & Chen, M. M.
System:
The UNT Digital Library
Indium phosphide/cadmium sulfide thin-film solar cells. Quarterly technical progress report No. 3, December 1979-April 1980
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.
System:
The UNT Digital Library
FLOWTRAN benchmarking with onset of flow instability data from 1988 Columbia University single-tube OFI experiment
Benchmarking FLOWTRAN, Version 16.2, with an Onset of Significant Voiding (OSV) criterion against measured Onset of Flow Instability (OFI) data from the 1988--89 Columbia University downflow tests has shown that FLOWTRAN with OSV is a conservative OFI predictor. Calculated limiting flow rates based on the Savannah River Site (SRS) OSV criterion were always higher than the measured flow rates at OFI. This work supplements recent FLOWTRAN benchmarking against 1963 downflow tests at Columbia University and 1988 downflow tests at the Heat Transfer Laboratory. These studies provide confidence that using FLOWTRAN with an OSV based criterion for SRS reactor limits analyses will generate operating limits that are conservative with respect to OFI, the criterion selected to prevent fuel damage.
Date:
June 1, 1990
Creator:
Chen, K.; Paul, P. K. & Barbour, K. L.
System:
The UNT Digital Library
Research, development and demonstration of nickel-iron batteries for electric vehicle propulsion. Annual report for 1979
Research progress in the development of Ni/Fe batteries (electrodes in particular) for the period is described. The negative plate demonstrated a reliable lifetime of almost 1000 cycles; 20 mm positive plates were proved feasible; prototype cells yielded output at about 50 Wh/kg and 100 Wh/liter; program goals of 20% greater than these figures appear feasible. 27 figures, 20 tables. (RWR)
Date:
June 1, 1980
Creator:
unknown
System:
The UNT Digital Library
CRITICAL EXPERIMENTS FOR THE PRELIMINARY DESIGN OF THE ARGONNE HIGH FLUX REACTOR
Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle,- Argonne High Flux Reactor, core. Data were obtained for flux distributions; cadmium ratios; temperature and void coefficients; and control rod, beam hole, and reflector worths. The data obtained furnished confirmation of theoretical predictions. The peak 2200-m/sec flux per unit power was measured as 3 x 10/sup 7/ n/(cm/sup 2/)(sec)(watt) for both cores. The two cores had internal H/sub 2/O thermal columns, 12.7 cm x 12.7 cm x 50.8 cm. These were enclosed by 100-liter fuel zones. The radial reflector was 90% beryllium containing 10% H/sub 2/0 plus Plexiglas by volume. The top and bottom reflectors were H/sub 2/O. The critical mass was 3.58 kg U/sup 235/ with a 1.16 metal-towater ratio in the fuel zone. The critical mass with a 1.60 metal- to-water ratio, taking into account 34.3 kg Type 304 stainless steel, was 7.15 kg U/sup 235/. (auth)
Date:
June 1, 1961
Creator:
de Villiers, J.W.L. ed.
System:
The UNT Digital Library
Radiochemical analyses of samples from beneath a solid radioactive waste disposal pit at Los Alamos, New Mexico
Solid radioactive wastes are disposed of by burial in pits excavated in rhyolite tuff at the Los Alamos Scientific Laboratory (LASL). Contaminants in the waste include fission products, uranium, and transuranic elements. In 1976, horizontal core holes were drilled beneath a waste disposal pit that was used from 1963 to 1966. Samples of the core were analyzed for gross alpha, gross beta, total uranium, /sup 90/Sr, /sup 137/Cs, /sup 238/Pu, /sup 239/ /sup 240/Pu, and /sup 241/Am. The measured gross alpha, gross beta, and uranium concentrations were above minimum detection limits; concentrations of the remaining radionuclides, all of which are man-made isotopes, were below the minimum detection limits. Statistical comparisons were made of the gross alpha, gross beta, and uranium data to identify any significant variations from natural concentrations in the tuff. The comparisons demonstrated that none of the radioactivity detected in the samples can be attributed to migration from the disposal pit.
Date:
June 1, 1980
Creator:
Purtymun, W. D.; Rogers, M. A. & Wheeler, M. L.
System:
The UNT Digital Library
Consumer Energy Atlas
This first edition of the Atlas provides, in reference form, a central source of information to consumers on key contacts concerned with energy in the US. Energy consumers need information appropriate to local climates and characteristics - best provided by state and local governments. The Department of Energy recognizes the authority of state and local governments to manage energy programs on their own. Therefore, emphasis has been given to government organizations on both the national and state level that influence, formulate, or administer policies affecting energy production, distribution, and use, or that provide information of interest to consumers and non-specialists. In addition, hundreds of non-government energy-related membership organizations, industry trade associations, and energy publications are included.
Date:
June 1, 1980
Creator:
unknown
System:
The UNT Digital Library
Performance study of the TFTR diagnostic neutral beam for active charge exchange measurements
A neutral beam source will be incorporated in the Tokamak Fusion Test Reactor (TFTR) charge exchange diagnostic to provide a time modulated, spatially localized enhancement of the charge exchange efflux. Two autonomous Charge Exchange Neutral Analyzer (CENA) systems are being designed for the TFTR. One system measures the plasma ion temperature along twelve vertical line-of-sight chords spaced approximately equidistantly across the torus minor diameter. The other system is dedicated primarily to measurement of ion phenomena associated with neutral beam injection heating and has a fan-like field of view along eight sight-lines in the equitorial plane. The neutral beam is steerable in order to access the viewing field of both CENA systems, though in general not simultaneously. The performance of the diagnostic neutral beam is evaluated to determine the optimal beam specifications for active charge exchange measurements. Using the optimal beam design parameters, the efficacy of the neutral doping is examined for both CENA systems over the envisioned range of the TFTR plasma density and temperature.
Date:
June 1, 1980
Creator:
Medley, S. S.; Goldston, R. J. & Towner, H. H.
System:
The UNT Digital Library
COMPILER INTO GEORGE ASSEMBLY ROUTINE
This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source language is roughly equal to that of Fortransit or SALT. (auth)
Date:
June 1, 1962
Creator:
George, R.
System:
The UNT Digital Library
Removal of silica from Raft River geothermal water
Lack of sufficient quantities of clean surface or near-surface water at Raft River for cooling purposes dictates that cooled geothermal fluid, effluent from the Raft River 5 MW(e) Pilot Power Plant, must also be used as condenser coolant. Prior testing revealed that a water-treatment system would be required to reduce silica and calcium concentrations of the cooling fluid. The water-treatment system specified was to use dolomitic lime for both pH adjustment and source of magnesium. The dolomitic lime treatment was investigated and found to be inadequate. Subsequent testing was done to find chemical systems that would adequately reduce silica concentrations. Three magnesium and two iron compounds were found which reduced silica to acceptable concentration levels. They are magnesium bicarbonate, magnesium chloride, magnesium sulfate, iron sulfate, and iron chloride. Magnesium oxide, using a two-stage countercurrent process, will also reduce silica to adequate levels.
Date:
June 1, 1980
Creator:
Suciu, D. F. & Miller, R. L.
System:
The UNT Digital Library
Low-Btu coal-gasification-process design report for Combustion Engineering/Gulf States Utilities coal-gasification demonstration plant. [Natural gas or No. 2 fuel oil to natural gas or No. 2 fuel oil or low Btu gas]
This report describes a coal gasification demonstration plant that was designed to retrofit an existing steam boiler. The design uses Combustion Engineering's air blown, atmospheric pressure, entrained flow coal gasification process to produce low-Btu gas and steam for Gulf States Utilities Nelson No. 3 boiler which is rated at a nominal 150 MW of electrical power. Following the retrofit, the boiler, originally designed to fire natural gas or No. 2 oil, will be able to achieve full load power output on natural gas, No. 2 oil, or low-Btu gas. The gasifier and the boiler are integrated, in that the steam generated in the gasifier is combined with steam from the boiler to produce full load. The original contract called for a complete process and mechanical design of the gasification plant. However, the contract was curtailed after the process design was completed, but before the mechanical design was started. Based on the well defined process, but limited mechanical design, a preliminary cost estimate for the installation was completed.
Date:
June 1, 1982
Creator:
Andrus, H E; Rebula, E; Thibeault, P R & Koucky, R W
System:
The UNT Digital Library
Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor
This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fission products. The analysis demonstrates that the concentrations of the key fission products I-131 and Sr-90 are far below the limits allowed by the technical specification.
Date:
June 1, 1982
Creator:
Burnette, R. D.
System:
The UNT Digital Library