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  Partner: UNT Libraries Government Documents Department
 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 ...
Contributing Partner: UNT Libraries Government Documents Department
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.
Contributing Partner: UNT Libraries Government Documents Department
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.
Contributing Partner: UNT Libraries Government Documents Department
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
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 ...
Contributing Partner: UNT Libraries Government Documents Department