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 Collection: Technical Report Archive and Image Library
Laboratory Testing of Glasses for Lockheed Idaho Technology Co. Fiscal Year 1994 Report

Laboratory Testing of Glasses for Lockheed Idaho Technology Co. Fiscal Year 1994 Report

Date: April 1995
Creator: Ellison, A. J. G.; Wolf, S. F. & Bates, John K.
Description: The purpose of this project is to measure the intermediate and long-term durability of vitrified waste forms developed by Lockheed Idaho Technology Co. (LITCO) for the immobilization of calcined radioactive wastes at Idaho National Engineering Laboratory. Two vitreous materials referred to as Formula 127 and Formula 532, have been subjected to accelerated durability tests to measure their long-term performance. Formula 127 consists of a glass matrix containing 5-10 vol % fluorite (CaF2) as a primary crystalline phase. It shows low releases of glass components to solution in 7-, 28-, 70-, and 140-day Product Consistency Tests performed at 2000 m⁻¹ at 90 C. In these tests, release rates for glass-forming components were similar to those found for durable waste glasses. The Ca and F released by the glass as it corrodes appear to re-precipitate as fluorite. Formula 532 consists of a glass matrix containing 5-10 vol % of an Al-Si-rich primary crystalline phase. The release rates for components other than aluminum are relatively low, but aluminum is released at a much higher rate than is typical for durable waste glasses. Secondary crystalline phases form relatively early during the corrosion of Formula 532 and appear to consist almost entirely of the Al-Si-rich ...
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Weight Losses of Marble and Limestone Briquettes Exposed to Outdoor Environment in the Eastern United States: Results of Exposure 1988-1992

Weight Losses of Marble and Limestone Briquettes Exposed to Outdoor Environment in the Eastern United States: Results of Exposure 1988-1992

Date: April 1995
Creator: Reimann, K. J.
Description: Monitoring continued on weight changes in marble and limestone briquettes exposed to the outdoor environment at sites in the eastern US. This report presents data for the exposure period 1988 - 1992 and summarizes results for the entire period from 1984. Since 1989, only three exposure sites have remained active, but briquettes from pre-exposed material were added at those sites. A linear relationship was found between cumulative gravimetric losses and exposure period. These losses resulted in an average recession rate of 11 to 21 micrometers/yr for marble and 21 to 45 micrometers/yr for limestone. The recession rates are site-dependent and can be described with respect to rain depth and other atmospheric conditions, as evidenced by the very low rates at the Ohio site on the movable rack, dry regime. Weight monitoring is continuing in a planned 10-year program.
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Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994

Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994

Date: March 1995
Creator: Buck, E. C.; Brown, N. R. & Dietz, N. L.
Description: A combination of backscattered electron imaging and analytical electron microscopy (AEM) with electron diffraction have been used to determine the physical and chemical properties of uranium contamination in soils from the Fernald Environmental Management Project in Ohio. The information gained from these studies has been used in the development and testing of remediation technologies.
Contributing Partner: UNT Libraries Government Documents Department
The Effects of the Glass Surface Area/Solution Volume Ratio on Glass Corrosion: a Critical Review

The Effects of the Glass Surface Area/Solution Volume Ratio on Glass Corrosion: a Critical Review

Date: March 1995
Creator: Ebert, William L.
Description: This report reviews and summarizes the present state of knowledge regarding the effects of the glass surface area/solution volume (SA/V) ratio on the corrosion behavior of borosilicate waste glasses.
Contributing Partner: UNT Libraries Government Documents Department
Equipment Decontamination: a Brief Survey of the DOE Complex

Equipment Decontamination: a Brief Survey of the DOE Complex

Date: March 1995
Creator: Conner, C.; Chamberlain, D. B.; Chen, L. & Vandegrift, G. F.
Description: Deactivation at DOE facilities has left a tremendous amount of contaminated equipment behind. In-situ methods are needed to decontaminate the interiors of the equipment sufficiently to allow either free release or land disposal. A brief survey was completed of the DOE complex on their needs for equipment decontamination with in-situ technology to determine (1) the types of contamination problems within the DOE complex, (2) decontamination processes that are being used or are being developed within the DOE, and (3) the methods that are available to dispose of spent decontamination solutions. In addition, potential sites for using testing decontamination methods were located. Based on the information obtained from these surveys, the Rocky Flats Plants and the Idaho National Engineering Laboratory appear to be best suited complete the initial testing of the decontamination processes.
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Treatment of Plutonium-Bearing Solutions: a Brief Survey of the DOE Complex

Treatment of Plutonium-Bearing Solutions: a Brief Survey of the DOE Complex

Date: March 1995
Creator: Conner, C.; Chamberlain, D. B.; Chen, L. & Vandegrift, G. F.
Description: With the abrupt shutdown of some DOE facilities, a significant volume of in-process material was left in place and still requires treatment for interim storage. Because the systems containing these process streams have deteriorated since shutdown, a portable system for treating the solutions may be useful. A brief survey was made of the DOE complex on the need for a portable treatment system to treat plutonium-bearing solutions. A survey was completed to determine (1) the compositions and volumes of solutions and heels present, (2) the methods that have been used to treat these solutions and heels in the past, and (3) the potential problems that exist in removing and treating these solutions. Based on the surveys and on the Defense Nuclear Facilities Safety Board Recommendation 94-1, design criteria for a portable treatment system were generated.
Contributing Partner: UNT Libraries Government Documents Department
Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1970-1992  : the JANUS Program Survival and Pathology Data

Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1970-1992 : the JANUS Program Survival and Pathology Data

Date: February 1995
Creator: Grahn, D.; Wright, B. J.; Carnes, B. A.; Williamson, F. S. & Fox, C.
Description: A research reactor for exclusive use in experimental radiobiology was designed and built at Argonne National Laboratory in the 1960`s. It was located in a special addition to Building 202, which housed the Division of Biological and Medical Research. Its location assured easy access for all users to the animal facilities, and it was also near the existing gamma-irradiation facilities. The water-cooled, heterogeneous 200-kW(th) reactor, named JANUS, became the focal point for a range of radiobiological studies gathered under the rubic of "the JANUS program". The program ran from about 1969 to 1992 and included research at all levels of biological organization, from subcellular to organism. More than a dozen moderate- to large-scale studies with the B6CF₁ mouse were carried out; these focused on the late effects of whole-body exposure to gamma rays or fission neutrons, in matching exposure regimes. In broad terms, these studies collected data on survival and on the pathology observed at death. A deliberate effort was made to establish the cause of death. This archieve describes these late-effects studies and their general findings. The database includes exposure parameters, time of death, and the gross pathology and histopathology in codified form. A series of appendices describes all ...
Contributing Partner: UNT Libraries Government Documents Department
Yucca Mountain Project - Argonne National Laboratory Annual Progress Report, FY 1994

Yucca Mountain Project - Argonne National Laboratory Annual Progress Report, FY 1994

Date: February 1995
Creator: Bates, John K.
Description: This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Evaporator Technology Progress Report FY 1992

Advanced Evaporator Technology Progress Report FY 1992

Date: January 1995
Creator: Chamberlain, D. B.
Description: This report summarizes the work that was completed in FY 1992 on the program "Technology Development for Concentrating Process Streams." The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and vapor-liquid equilibrium data are needed to design an effective process for concentrating process streams. Therefore, literature surveys were completed and are summarized in this report. A model that is being developed to predict vapor phase compositions is described. A laboratory-scale evaporator was purchased and installed to study the evaporation process and to collect additional data. This unit is described in detail. Two new LICON evaporators are being designed for installation ...
Contributing Partner: UNT Libraries Government Documents Department
Archean and Early Proterozoic Tectonic Framework of North-Central United States and Adjacent Canada

Archean and Early Proterozoic Tectonic Framework of North-Central United States and Adjacent Canada

Date: 1995
Creator: Sims, P. K. (Paul Kibler), 1918-2011
Description: From abstract: This report contains the analysis of the southern part of the Canadian Shield and the subsurface of the southern interior platform where they comprise two Archean cratons and three Early Proterozoic collisional orogens.
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Boiling Heat Transfer with Three Fluids in Small Circular and Rectangular Channels

Boiling Heat Transfer with Three Fluids in Small Circular and Rectangular Channels

Date: January 1995
Creator: Tran, T. N.; Wambsganss, M. W. & France, D. M.
Description: Small circular and noncircular channels are representative of flow passages act evaporators and condensers. This report describes results of an experimental study on heat transfer to the flow boiling of refrigerants (R-12) and refrigerant-134a (R-134a) in a small horizontal circular-cross-section tube. The tube diameter of 2.46 mm was chosen to approximate the hydraulic diameter of a 4.06 x 1.70 mm rectangular channel previously studied with R-12, and a 2.92-mm-diameter circular tube previously studied with R-113. The objective of this study was to assess the effects of channel geometry and fluid properties on the heat transfer coefficient and to obtain additional insights relative to the heat transfer mechanism(s). The current circular flow channel for the R-12 and R-134a tests was made of brass and had an overall length of 0.9 in. The channel wall was electrically heated, and thermocouples were installed on the channel wall and in the bulk fluid stream. Voltage taps were located at the same axial locations as the stream thermocouples to allow testing over an exit quality range to 0.94 and a large range of mass flux (58 to 832 kg/m sq s) and heat flux (3.6 to 59 kW/m sq). Saturation pressure was nearly constant, averaging ...
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Carbon Dioxide in Mississippian Rocks of the Paradox Basin and Adjacent Areas, Colorado, Utah, New Mexico, and Arizona

Carbon Dioxide in Mississippian Rocks of the Paradox Basin and Adjacent Areas, Colorado, Utah, New Mexico, and Arizona

Date: 1995
Creator: Cappa, James A. & Rice, Dudley D.
Description: From abstract: This report is about six gas samples that were obtained from the Mississippian Leadville Limestone in the McElmo field, Colorado, and the Lisbon field, Utah. These samples were recorded to contain a high reading of carbon dioxide and the report investigates these results.
Contributing Partner: UNT Libraries Government Documents Department
Fluvial Architecture of the Lower Cretaceous Lakota Formation, Southwestern Flank of the Black Hills Uplift, South Dakota

Fluvial Architecture of the Lower Cretaceous Lakota Formation, Southwestern Flank of the Black Hills Uplift, South Dakota

Date: 1995
Creator: Dahlstrom, David J. & Fox, J. E.
Description: From introduction This report describes large-scale depositional units referred to as architectural elements, interpreted from outcrops of three distinct fluvial sandstone units of the Lakota Formation in the southwestern Black Hills area of Custer and Fall River Counties, South Dakota. These fluvial deposits formed near the end of an episode of continental deposition that began when the Jurassic Sundance sea regressed from the region and ended when the Early Cretaceous Skull Creek sea encroached from the north in Albian time.
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Geology of Pre-Pennsylvanian Rocks in the Paradox Basin and Adjacent Areas, Southeastern Utah and Southwestern Colorado

Geology of Pre-Pennsylvanian Rocks in the Paradox Basin and Adjacent Areas, Southeastern Utah and Southwestern Colorado

Date: 1995
Creator: Condon, Steven M.
Description: From abstract: This report is about the geology of pre-Pennsylvanian rocks in the Paradox basin and its adjacent areas--such as the Mississippian strata, the Upper Devonian rocks, and the Upper Cambrian--in southeastern Utah and southwestern Colorado.
Contributing Partner: UNT Libraries Government Documents Department
Regional Potential of Selected Paleozoic Carbonate Units in the Northern Midcontinent for Undiscovered Mississippi Valley-Type Deposits

Regional Potential of Selected Paleozoic Carbonate Units in the Northern Midcontinent for Undiscovered Mississippi Valley-Type Deposits

Date: 1995
Creator: Pratt, Walden P.
Description: From abstract: This report attempts to identify areas where geologic conditions for the Mississippi Valley-type (MVT) deposits are favorable.
Contributing Partner: UNT Libraries Government Documents Department
Separation Science and Technology Semiannual Progress Report for October 1992 - March 1993

Separation Science and Technology Semiannual Progress Report for October 1992 - March 1993

Date: January 1995
Creator: Vandegrift, G. F.
Description: This document reports on the work done by the Separations Science and Technology Section of the Chemical Technology Division, Argonne National Laboratory, in the period October 1992-March 1993. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements.
Contributing Partner: UNT Libraries Government Documents Department
Development Program for Magnetically Assisted Chemical Separation : Evaluation of Cesium Removal from Hanford Tank Supernatant

Development Program for Magnetically Assisted Chemical Separation : Evaluation of Cesium Removal from Hanford Tank Supernatant

Date: December 1994
Creator: Nuñez, Luis
Description: Magnetic particles (MAG*SEP(sup SM)) coated with various absorbents were evaluated for the separation and recovery of low concentrations of cesium from nuclear waste solutions. The MAG*SEP(sup SM) particles were coated with (1) clinoptilolite, (2) transylvanian volcanic tuff, (3) resorcinol formaldehyde, and (4) crystalline silico-titanate, and then were contacted with a Hanford supernatant simulant. Particles coated with the crystalline silico-titanate were identified by Bradtec as having the highest capacity for cesium removal under the conditions tested (variation of pH, ionic strength, cesium concentration, and absorbent/solution ratio). The MAG*SEP(sup SM) particles coated with resorcinol formaldehyde had high distribution ratios values and could also be used to remove cesium from Hanford supernant simulant. Gamma irradiation studies were performed on the MAG*SEP(sup SM) particles with a gamma dose equivalent to 100 cycles of use. This irradiation decreased the loading capacity and distribution ratios for the particles by greater than 75%. The particles demonstrated high sensitivity to radiolytic damage due to the degradation of the polymeric regions. These results were supported by optical microscopy measurements. Overall, use of magnetic particles for cesium separation under nuclear waste conditions was found to be marginally effective.
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Sludge Technology Assessment

Sludge Technology Assessment

Date: December 1994
Creator: Krause, T. R.; Cunnane, J. C. & Helt, J. E.
Description: This document is intended to (1) identify separation technologies which are being considered for sludge treatment at various DOE sites, (2) define the current state of sludge treatment technology, (3) identify what research and development is required, (4) identify current research programs within either DOE or academia developing sludge treatment technology, and (5) identify commercial separation technologies which may be applicable. Due to the limited scope of this document, technical evaluations regarding the need for a particular separations technology, the current state of development, or the research required for implementation, are not provided.
Contributing Partner: UNT Libraries Government Documents Department
Methods for Removing Transuranic Elements from Waste Solutions

Methods for Removing Transuranic Elements from Waste Solutions

Date: November 1994
Creator: Slater, S. L.; Chamberlain, D. B.; Conner, C.; Sedlet, J.; Srinivasan, B. & Vandegrift, G. F.
Description: This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant.
Contributing Partner: UNT Libraries Government Documents Department
Analytical Electron Microscopy Characterization of Uranium-Contaminated Soils from the Fernald Site, FY1993 Report

Analytical Electron Microscopy Characterization of Uranium-Contaminated Soils from the Fernald Site, FY1993 Report

Date: October 1994
Creator: Buck, E. C.; Cunnane, J. C.; Brown, N. R. & Dietz, N. L.
Description: A combination of optical microscopy, scanning electron microscopy with backscattered electron detection (SEM/BSE), and analytical electron microscopy (AEM) is being used to determine the nature of uranium in soils from the Fernald Environmental Management Project. The information gained from these studies is being used to develop and test remediation technologies. Investigations using SEM have shown that uranium is contained within particles that are typically 1 to 100 micrometers in diameter. Further analysis with AEM has shown that these uranium-rich regions are made up of discrete uranium-bearing phases. The distribution of these uranium phases was found to be inhomogeneous at the microscopic level.
Contributing Partner: UNT Libraries Government Documents Department
Practical Superconductor Development for Electrical Power Applications, Annual Report: 1994

Practical Superconductor Development for Electrical Power Applications, Annual Report: 1994

Date: October 1994
Creator: Argonne National Laboratory. Materials and Components Technology Division.
Description: Annual report for the superconductor program at Argonne National Laboratory discussing the group's activities and research. This report describes technical progress of research and development efforts aimed at producing superconducting components in the Y-Ba-Cu, (Bi,Pb)-Sr-Ca-Cu, (Tl,Pb,Bi)-(Ba,Sr)-Ca-Cu, and Hg-Ba-Ca-Cu-O oxide systems including: synthesis and heat treatment of high-Ta superconductors, formation of monolithic and composite conductors, characterization of structures and superconducting and mechanical properties, and fabrication and testing of prototype components.
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European Fuel Cells R & D Review. Final Report, Purchase Order No. 062014

European Fuel Cells R & D Review. Final Report, Purchase Order No. 062014

Date: September 1994
Creator: Michael, Philip D. & Maguire, J.
Description: The aim of the Review is to present a statement on the status of fuel cell development in Europe, addressing the research, development and demonstration (RD & D) and commercialization activities being undertaken, identifying key European organizations active in development and commercialization of fuel cells and detailing their future plans. This document describes the RD & D activities in Europe on alkaline, phosphoric acid, polymer electrolyte, direct methanol, solid oxide, and molten carbonate fuel cell types. It describes the European Commission`s activities, its role in the European development of fuel cells, and its interaction with the national programs. It then presents a country-by-country breakdown. For each country, an overview is given, presented by fuel cell type. Scandinavian countries are covered in less detail. American organizations active in Europe, either in supplying fuel cell components, or in collaboration, are identified. Applications include transportation and cogeneration.
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Extensible PDE Solvers Package Users Manual

Extensible PDE Solvers Package Users Manual

Date: September 1994
Creator: Smith, Barry
Description: This manual describes the use of the Extensible PDE Solvers package for the solution of elliptic PDEs.
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Magnetically Assisted Chemical Separation (MACS) Process : Preparation and Optimization of Particles for Removal of Transuranic Elements

Magnetically Assisted Chemical Separation (MACS) Process : Preparation and Optimization of Particles for Removal of Transuranic Elements

Date: September 1994
Creator: Nuñez, Luis; Kaminiski, M.; Bradley, C.; Buchholz, B. A.; Landsberger, S.; Aase, S. B. et al.
Description: This report describes the development of a separation process for TRU elements from various high-level waste streams.
Contributing Partner: UNT Libraries Government Documents Department