You limited your search to:

  Partner: UNT Libraries Government Documents Department
 Collection: Technical Report Archive and Image Library
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
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.
Contributing Partner: UNT Libraries Government Documents Department
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.
Contributing Partner: UNT Libraries Government Documents Department
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.
Contributing Partner: UNT Libraries Government Documents Department