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500-kW DCHX pilot-plant evaluation testing (open access)

500-kW DCHX pilot-plant evaluation testing

Field tests with the 500 kW Direct Contact Pilot Plant were conducted utilizing brine from well Mesa 6-2. The tests were intended to develop comprehensive performance data, design criteria, and economic factors for the direct contact power plant. The tests were conducted in two phases. The first test phase was to determine specific component performance of the DCHX, turbine, condensers and pumps, and to evaluate chemical mass balances of non-condensible gases in the IC/sub 4/ loop and IC/sub 4/ in the brine stream. The second test phase was to provide a longer term run at nearly fixed operating conditions in order to evaluate plant performance and identify operating cost data for the pilot plant. During these tests the total accumulated run time on major system components exceeded 1180 hours with 777 hours on the turbine prime mover. Direct contact heat exchanger performance exceeded the design prediction.
Date: October 1, 1981
Creator: Hlinak, A.; Lee, T.; Loback, J.; Nichols, K.; Olander, R.; Oshmyansky, S. et al.
Object Type: Report
System: The UNT Digital Library
ACDOS2: a code for neutron-induced activities and dose rates (open access)

ACDOS2: a code for neutron-induced activities and dose rates

In order to anticipate problems from the radioactivation of neutral beam sources as a result of testing, a code has been developed which calculates both the radioactivities produced and the dose rates resulting therefrom. The code ACDOS2 requires neutron source strength and spectral distribution as input, or alternately, the source strength can be calculated internally from an input of neutral beam source parameters. A variety of simple geometries can be specified, and up to 12 times of interest following the shutdown of the neutron source. Radiation attenuating and daughter radioactivities are treated accurately. ACDOS2 is also of use for neutron-induced radioactivation problems involving accelerators, fusion reactors, or fission reactors.
Date: October 1, 1981
Creator: Ruby, L.; Keney, G.S. & Lagache, J.C.
Object Type: Article
System: The UNT Digital Library
Actinide leaching from waste glass: air-equilibrated versus deaerated conditions (open access)

Actinide leaching from waste glass: air-equilibrated versus deaerated conditions

Leach tests were conducted in aerated and deaerated solutions using glass containing /sup 239/Pu, /sup 237/Np and /sup 238/U, at temperatures of 25 and 75/sup 0/C and in deionized water, 0.03M NaHCO/sub 3/ and WIPP B salt brine for periods up to 341 days. Neptunium leaching was decreased by factors of 10 to 100 (depending on leach time) in the deaerated solutions at 75/sup 0/C. Plutonium leaching decreased by factors of 3 to 5 due to deaeration, but only in the deionized water leachate at 25/sup 0/C. Uranium leaching in salt brine and deionized water at 25/sup 0/C was decreased by factors of 2 to 5 in deaerated solutions. Time and temperature dependencies were also observed for the leaching of the actinides during the course of this work. After the first leach interval (2 days), the time dependent release curve for Pu was essentially flat or decreasing under all conditions, and maximum Pu solution concentration (at 25/sup 0/C), as implied by release in aerated leachate, agrees with independent solubility data. The low /sup 239/Pu releases observed in leach solutions are consistent with accumulation of /sup 239/Pu on the leached glass surface. The amounts of uranium and neptunium leached increased with …
Date: October 1, 1981
Creator: Peters, R. D. & Diamond, H.
Object Type: Report
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 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
The Age, Volume 2, Number 11, October 1, 1981 (open access)

The Age, Volume 2, Number 11, October 1, 1981

Monthly publication containing information related to Chambers County, Texas, including current events of the Chambers County Historical Commission, the Wallisville Heritage Park, and the Chambers County historical and genealogical societies; reprinted newspaper articles about county events and citizens; and historical news and records.
Date: October 1, 1981
Creator: Wallisville Heritage Park (Organization)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
[Agreement between Ray D. Hetrick and Richard and Patricia Darville, October 1, 1981] (open access)

[Agreement between Ray D. Hetrick and Richard and Patricia Darville, October 1, 1981]

Document detailing the terms of a loan agreement between Ray D. Hetrick and Richard and Patricia Darville. Hetrick will pay the Darville $1,600 over a period of 16 months, with no interest.
Date: October 1, 1981
Creator: Hetrick, Ray D.; Darville, Richard & Darville, Patricia
Object Type: Legal Document
System: The Portal to Texas History
The Albany News (Albany, Tex.), Vol. 106, No. 15, Ed. 1 Thursday, October 1, 1981 (open access)

The Albany News (Albany, Tex.), Vol. 106, No. 15, Ed. 1 Thursday, October 1, 1981

Weekly newspaper from Albany, Texas that includes local, state and national news along with extensive advertising.
Date: October 1, 1981
Creator: Lucas, Donnie
Object Type: Newspaper
System: The Portal to Texas History
All-metal vacuum chamber for the ZT-40 experiment (open access)

All-metal vacuum chamber for the ZT-40 experiment

We discuss the design and fabrication of the all-metal vacuum chamber presently in use in the ZT-40 device. ZT-40 is the current experiment in the Los Alamos Reversed-Field Pinch (RFP) program. The new vessel, which replaces a ceramic one, is made of Inconel 625 and has major and minor diameters of 228 cm and 40 cm, respectively. It consists of 24 convoluted and straight sections welded into a single toroidal geometry. Presented are several design features showing diagnostic and vacuum port tubulations and thermal-electrical insulation isolating the unit from its conducting shell. We also discuss fabrication techniques and our procedure for cleaning and heat treatment designed to eliminate residual gas contamination in the Inconel material.
Date: October 1, 1981
Creator: Dike, R. S. & Downing, J. N.
Object Type: Article
System: The UNT Digital Library
The Allen American (Allen, Tex.), Vol. 12, No. 22, Ed. 1 Thursday, October 1, 1981 (open access)

The Allen American (Allen, Tex.), Vol. 12, No. 22, Ed. 1 Thursday, October 1, 1981

Semiweekly newspaper from Allen, Texas that includes local, state, and national news along with advertising.
Date: October 1, 1981
Creator: Johnson, Sherry
Object Type: Newspaper
System: The Portal to Texas History
Alpha-transfer reactions (open access)

Alpha-transfer reactions

Some of the essential features of the experimental results and theoretical interpretations of ..cap alpha..-transfer reactions are summarized. (WHK)
Date: October 1, 1981
Creator: Betts, R.R.
Object Type: Article
System: The UNT Digital Library
The Alto Herald and The Wells News 'N Views (Alto, Tex.), Vol. 85, No. 21, Ed. 1 Thursday, October 1, 1981 (open access)

The Alto Herald and The Wells News 'N Views (Alto, Tex.), Vol. 85, No. 21, Ed. 1 Thursday, October 1, 1981

Weekly newspaper from Alto, Texas that includes local, state, and national news along with extensive advertising.
Date: October 1, 1981
Creator: unknown
Object Type: Newspaper
System: The Portal to Texas History
The Altus Times (Altus, Okla.), Vol. 59, No. 236, Ed. 1 Thursday, October 1, 1981 (open access)

The Altus Times (Altus, Okla.), Vol. 59, No. 236, Ed. 1 Thursday, October 1, 1981

Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date: October 1, 1981
Creator: Gilmore, Robert K.; Hart, Sandra & Hale, Dave
Object Type: Newspaper
System: The Gateway to Oklahoma History
Analytic and experimental decay heat determinations of 800-MeV proton irradiated aluminum (open access)

Analytic and experimental decay heat determinations of 800-MeV proton irradiated aluminum

Postirradiation radiochemistry analysis of 800-MeV proton irradiated ultrahigh purity aluminum has been done with standard gamma-ray counting equipment determining the Na/sup 22/ activity in the activated aluminum. Results are compared to predicted values obtained from CINDER, a general nuclide depletion and fission-product code. This program can be used easily to calculate the activity of materials under arbitrary irradiation, provided that the source terms for the various radionuclides produced are known. The required production cross sections have been calculated by using the nucleon-meson transport code NMTC to determine the nuclear reactions produced by the protons, and the theory of Lindhard et al. to evaluate the resultant damage energy deposited in the target.
Date: October 1, 1981
Creator: Kmetyk, L. N. & Sommer, W. F.
Object Type: Report
System: The UNT Digital Library
Analytical and numerical calculations of field-reversed theta-pinch equilibria based on a generalized Hill's vortex model (open access)

Analytical and numerical calculations of field-reversed theta-pinch equilibria based on a generalized Hill's vortex model

We have been investigating methods for numerically extending the analytic solutions of field reversed theta pinch equilibria so that the results may be used in various stability and dynamics studies. We have used generalizations of elliptical Hill's vortex equilibria which accomodate separatrices with more rectangular shapes and which allow plasma to exist outside the separatrix. Although the equilibria are specified analytically inside the plasma surface, numerical techniques are required to generate the solution in the vacuum region. Two computer codes have been used in sequence. The first determines a set of external coils and their currents so that they match the known coil field inside the plasma. Then, given this coil field, we compute the contribution from the plasma currents to the fields in the vacuum region.
Date: October 1, 1981
Creator: Anderson, D. V.; Hammer, J. H. & Barnes, D. C.
Object Type: Article
System: The UNT Digital Library
Analytical methods for the determintion of some elements and Fe/sup +2/ to Fe/sup +3/ ratio in simulated sludges and Synroc formulations (open access)

Analytical methods for the determintion of some elements and Fe/sup +2/ to Fe/sup +3/ ratio in simulated sludges and Synroc formulations

Analytical methods for the determination of Fe, Al, Mn, Ca, Ni, Na, Sr, Cs, Ti, and Ba in simulated sludges and Synroc formulations are discussed. These are the elements that may be completed by atomic absorption spectroscopy, AAS. AAS methods are complicated by the dissolution methods used. These problems are discussed. In addition, the method used for the determination of Fe/sup +2/ to Fe/sup +3/ ratio is presented.
Date: October 1, 1981
Creator: Lim, R.
Object Type: Report
System: The UNT Digital Library
Application of foams to the processing of fabrics. Final report, October 1, 1977-September 30, 1981 (open access)

Application of foams to the processing of fabrics. Final report, October 1, 1977-September 30, 1981

The primary objective of this project was to reduce the energy consumed in the wet processing of fabrics where wet processing encompasses those processes used to convert loomstate (greige) goods to finished textile products. This includes desizing, scouring, bleaching, dyeing, printing, and finishing of fabrics. The energy intensive step in most of these processes is drying the fabric. By having less water on the fabric as it enters a drying oven, proportionately less energy is consumed in drying the fabric. The specific route used in this project to accomplish this objective has been to use air to distribute the finish, dye or printing ink onto the fabric. Rather than saturating the fabric with a dilute finish formulation, a concentrated formulation is mechanically foamed, air serving as the diluting medium and the foam applied to the fabric. In this manner, the water content of the fabric as it enters the drying oven is reduced by as much as 80% thereby leading to a corresponding reduction in the energy required to dry the fabric. Details on the procedure are presented and experimental results are discussed. (MCW)
Date: October 1, 1981
Creator: Namboodri, C.G.
Object Type: Report
System: The UNT Digital Library
Applications of NDA instrumentation in the Y-12 highly enriched uranium recovery facility (open access)

Applications of NDA instrumentation in the Y-12 highly enriched uranium recovery facility

This paper discusses an alternative to weighing and sampling which is coming into increasing use in Oak Ridge Y-12 Plant for obtaining the uranium content of heterogeneous compounds and mixtures. This technique, nondestructive analyses (NDA), is based on measuring the natural or induced radioactivity of the uranium contained in the by-product materials. Nondestructive analyses equipment has been used in Y-12 for many years for performing certain qualitative measurements. For example, materials for discard are routinely checked by NDA to verify that their uranium contamination is negligible. Recently, however, three quantitative NDA systems have been put into operation in Y-12. These include systems for measurement of low- and high-density solids and a system for analysis of solution samples. Also, a study of the feasibility of measuring the uranium content of solution streams in the uranium recovery facility has been carried out. These items are briefly discussed.
Date: October 1, 1981
Creator: Jeter, I. W.; Smith, S. E.; Hogue, H. H.; Bowers, G. L.; Russo, P. & Strittmatter, R.
Object Type: Article
System: The UNT Digital Library
Aquifer evaluation at Fenton Hill, October and November 1980 (open access)

Aquifer evaluation at Fenton Hill, October and November 1980

An aquifer test at the Fenton Hill Geothermal Site was performed on a volcanic aquifer used for water supply. The test was made to determine the yield from the aquifer and to predict the amount of depletion that would occur with increased production during the period 1981 to 1985. A step-discharge test indicated the aquifer would comfortably yield 100 gal per min (gpm) without excessive water level drawdown in the pumping well. Drawdown test results indicated that the average aquifer transmissivity and storage coefficient are 5000 gal per day per foot (gpd/ft) and 0.07, respectively. Using these parameters, a drawdown was estimated to be at least 42 ft at the pumping well due to a withdrawal of 500 acre-ft of water over 5 yr. However, the presence of ground water boundaries indicates the aquifer is of limited extent, and because of this, the water level decline would probably be much greater. Past water level data indicate that there is little recharge to the aquifer.
Date: October 1, 1981
Creator: Becker, N. M.; Purtymun, W. D. & Ballance, W. C.
Object Type: Report
System: The UNT Digital Library
Archer County News (Archer City, Tex.), No. 40, Ed. 1 Thursday, October 1, 1981 (open access)

Archer County News (Archer City, Tex.), No. 40, Ed. 1 Thursday, October 1, 1981

Weekly newspaper from Archer City, Texas that includes local, state and national news along with advertising.
Date: October 1, 1981
Creator: Lobpries, F. Mike & Lobpries, Fran
Object Type: Newspaper
System: The Portal to Texas History
Assessment of radiation doses from residential smoke detectors that contain americium-241 (open access)

Assessment of radiation doses from residential smoke detectors that contain americium-241

External dose equivalents and internal dose commitments were estimated for individuals and populations from annual distribution, use, and disposal of 10 million ionization chamber smoke detectors that contain 110 kBq (3 ..mu..Ci) americium-241 each. Under exposure scenarios developed for normal distribution, use, and disposal using the best available information, annual external dose equivalents to average individuals were estimated to range from 4 fSv (0.4 prem) to 20 nSv (2 ..mu..rem) for total body and from 7 fSv to 40 nSv for bone. Internal dose commitments to individuals under post disposal scenarios were estimated to range from 0.006 to 80 ..mu..Sv (0.0006 to 8 mrem) to total body and from 0.06 to 800 ..mu..Sv to bone. The total collective dose (the sum of external dose equivalents and 50-year internal dose commitments) for all individuals involved with distribution, use, or disposal of 10 million smoke detectors was estimated to be about 0.38 person-Sv (38 person-rem) to total body and 00 ft/sup 2/).
Date: October 1, 1981
Creator: O'Donnell, F. R.; Etnier, E. L.; Holton, G. A. & Travis, C. C.
Object Type: Report
System: The UNT Digital Library
ASTM standard recommended guide on application of ENDF/A cross section and uncertainty file: establishment of the file (open access)

ASTM standard recommended guide on application of ENDF/A cross section and uncertainty file: establishment of the file

A new ASTM Standard Recommended Guide on Application of ENDF/A Cross Section and Uncertainty File is in preparation by ASTM Committee E10 on Nuclear Technology and Applications. This ASTM Standard is being prepared in support of the standardization of physics-dosimetry procedures and data needed for Light Water Reactor (LWR) power plant pressure vessel and support structure materials surveillance and test reactor development programs. The main subject of this paper is the estabilishment of the ENDF/A Cross Section and Uncertainty File. The development of evaluated cross section files such as the evaluated nuclear data file, ENDF/B, has occurred mainly to meet the needs of physics calculators. These files are tested by calculations of well-measured benchmark problems such as reactivity or critical mass measurements. Data in the files have then been re-evaluated where disagreements with the benchmark measurements indicate data to be deficient.
Date: October 1, 1981
Creator: Lippincott, E.P. & McElroy, W.N.
Object Type: Article
System: The UNT Digital Library
Author's guide to publishing in the fields of plasma physics and controlled fusion (open access)

Author's guide to publishing in the fields of plasma physics and controlled fusion

None
Date: October 1, 1981
Creator: unknown
Object Type: Article
System: The UNT Digital Library
Automobile materials competition: energy implications of fiber-reinforced plastics (open access)

Automobile materials competition: energy implications of fiber-reinforced plastics

The embodied energy, structural weight, and transportation energy (fuel requirement) characteristics of steel, fiber-reinforced plastics, and aluminum were assessed to determine the overall energy savings of materials substitution in automobiles. In body panels, a 1.0-lb steel component with an associated 0.5 lb in secondary weight is structurally equivalent to a 0.6-lb fiber-reinforced plastic component with 0.3 lb in associated secondary weight or a 0.5-lb aluminum component with 0.25 lb of secondary weight. (Secondary weight refers to the combined weight of the vehicle's support structure, engine, braking system, and drive train, all of which can be reduced in response to a decrease in total vehicle weight.) The life cycle transportation energy requirements of structurally equivalent body panels (including their associated secondary weights) are 174.4 x 10/sup 3/ Btu for steel, 104.6 x 10/sup 3/ Btu for fiber-reinforced plastics, and 87.2 x 10/sup 3/ Btu for aluminum. The embodied energy requirements are 37.2 x 10/sup 3/ Btu for steel, 22.1 x 10/sup 3/ Btu for fiber-reinforced plastics, and 87.1 x 10/sup 3/ Btu for aluminum. These results can be combined to yield total energy requirements of 211.6 x 10/sup 3/ Btu for steel, 126.7 x 10/sup 3/ Btu for fiber-reinforced plastics, and …
Date: October 1, 1981
Creator: Cummings-Saxton, J.
Object Type: Report
System: The UNT Digital Library