Network maintenance July 27th between 7:30AM and 8:00AM CDT may cause service disruptions.

  You limited your search to:

 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
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.
Contributing Partner: UNT Libraries Government Documents Department
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
Separation Science and Technology Semiannual Progress Report: April - September 1992

Separation Science and Technology Semiannual Progress Report: April - September 1992

Date: September 1994
Creator: Vandegrift, G. F.
Description: This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April-September 1992. 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
Basic TRUEX Process for Rocky Flats Plant

Basic TRUEX Process for Rocky Flats Plant

Date: August 1994
Creator: Leonard, R. A.; Chamberlain, D. B.; Dow, J. A.; Farley, S. E.; Nuñez, Luis; Regalbuto, M. C. et al.
Description: The Generic TRUEX Model was used to develop a TRUEX process flowsheet for recovering the transuranics (plutonium, americium) from a nitrate waste stream at Rocky Flats Plant. T\
Contributing Partner: UNT Libraries Government Documents Department
Physics Division Annual Review: April 1, 1993-March 31, 1994

Physics Division Annual Review: April 1, 1993-March 31, 1994

Date: August 1994
Creator: Argonne National Laboratory. Physics Division.
Description: Annual report of activities of the Argonne National Laboratory Physics Division, including heavy-ion nuclear physics research, operation and development of ATLAS, medium-energy nuclear physics research, theoretical physics, atomic and molecular physics research.
Contributing Partner: UNT Libraries Government Documents Department
Technology Development Goals for Automotive Fuel Cell Power Systems : Final Report, Contract No. 22822402

Technology Development Goals for Automotive Fuel Cell Power Systems : Final Report, Contract No. 22822402

Date: August 1994
Creator: James, Brian D.; Baum, George N. & Kuhn, Ira F.
Description: This report determines cost and performance requirements for Proton Exchange Membrane (PEM) fuel cell vehicles carrying pure hydrogen fuel, to achieve parity with internal combustion engine (ICE) vehicles.
Contributing Partner: UNT Libraries Government Documents Department
Users Manual for KSP Data-Structure-Neutral Codes Implementing Krylov Space Methods

Users Manual for KSP Data-Structure-Neutral Codes Implementing Krylov Space Methods

Date: August 1994
Creator: Gropp, William & Smith, Barry
Description: The combination of a Krylov space method and a pre-conditioner is at the heart of most modern numerical codes for the iterative solution of linear systems. This document contains both a users manual and a description of the implementation for the Krylov space methods package KSP included as part of the Portable, Extensible Tools for Scientific computation package (PETSc). PETSc is a large suite of data-structure-neutral libraries for the solution of large-scale problems in scientific computation, in particular on massively parallel computers. The methods in KSP are conjugate gradient method, GMRES, BiCG-Stab, two versions of transpose-free QMR, and others. All of the methods are coded using a common, data-structure-neutral framework and are compatible with the sequential, parallel, and out-of-core solution of linear systems. The codes make no assumptions about the representation of the linear operator; implicitly defined operators (say, calculated using differencing) are fully supported. In addition, unlike all other iterative packages we are aware of, the vector operations are also data-structure neutral. Once certain vector primitives are provided, the same KSP software runs unchanged using any vector storage format. It is not restricted to a few common vector representations. The codes described are actual working codes that run on ...
Contributing Partner: UNT Libraries Government Documents Department
Critical Review of Glass Performance Modeling

Critical Review of Glass Performance Modeling

Date: July 1994
Creator: Bourcier, William L.
Description: Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic repository. Mechanistic chemical models are used to predict the rate at which radionuclides will be released from the glass under repository conditions. The most successful and useful of these models link reaction path geochemical modeling programs with a glass dissolution rate law that is consistent with transition state theory. These models have been used to simulate several types of short-term laboratory tests of glass dissolution and to predict the long-term performance of the glass in a repository. Although mechanistically based, the current models are limited by a lack of unambiguous experimental support for some of their assumptions. The most severe problem of this type is the lack of an existing validated mechanism that controls long-term glass dissolution rates. Current models can be improved by performing carefully designed experiments and using the experimental results to validate the rate-controlling mechanisms implicit in the models. These models should be supported with long-term experiments to be used for model validation. The mechanistic basis of the models should be explored by using modern molecular simulations such as molecular orbital and molecular dynamics to investigate both the glass structure and ...
Contributing Partner: UNT Libraries Government Documents Department
ANL Technical Support Program for DOE Environmental Restoration and Waste Management

ANL Technical Support Program for DOE Environmental Restoration and Waste Management

Date: June 1994
Creator: Bates, John K.; Bourcier, W. L.; Bradley, C. R.; Brown, N. R.; Buck, E. C.; Carroll, S. A. et al.
Description: A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
Contributing Partner: UNT Libraries Government Documents Department
Development of a Small-Channel Nucleate-Boiling Heat Transfer Correlation

Development of a Small-Channel Nucleate-Boiling Heat Transfer Correlation

Date: June 1994
Creator: Kasza, Kenneth Edmund & Wambsganss, M. W.
Description: Development of an improved semi-mechanistic-based set of correlation parameters for nucleation-dominant flow-boiling heat transfer in small channels is described.
Contributing Partner: UNT Libraries Government Documents Department
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1993

Argonne National Laboratory-East Site Environmental Report for Calendar Year 1993

Date: May 1994
Creator: Golchert, N. W. & Kolzow, R. G.
Description: This annual report on the ANL environmental protection program provides the DOE, environmental agencies, and the public with information on the levels of radioactive and chemical pollutants in the vicinity of ANL and on the amounts, if any, added to the environment by ANL operations. It also summarizes compliance of ANL operations with applicable environmental laws and regulations and highlights significant accomplishments and problems related to environmental protection. The report follows the guidelines given in DOE Order 5400.1.
Contributing Partner: UNT Libraries Government Documents Department
First Assessment of Computations of Turbulent Bubbly Flow and Particulate Flow with the COMMIX-M Program

First Assessment of Computations of Turbulent Bubbly Flow and Particulate Flow with the COMMIX-M Program

Date: May 1994
Creator: Bottoni, M.; Chang, F. C. & Ding, J.
Description: The COMMIX-M computer code, which describes steady-state and transient single- and multi-component flows in engineering systems, has been implemented to simulate suspension flows in laminar regimes and turbulent and bubbly particulate flows. This report presents a synopsis of the present code's capabilities, with particular emphasis on the recent development of turbulence models, and explains in detail the modifications necessary to simulate particulate flows and bubbly flows. First results of computations of turbulent bubbly and particulate flows are then given and compared with results of computations reported in the literature and with preliminary experimental results obtained at the Kernforschungszentrum Karlsruhe (Germany).
Contributing Partner: UNT Libraries Government Documents Department
Glassy Slags for Minimum Additive Waste Stabilization: Interim Progress Report, May 1993-February 1994

Glassy Slags for Minimum Additive Waste Stabilization: Interim Progress Report, May 1993-February 1994

Date: May 1994
Creator: Feng, X.; Wronkiewicz, David J.; Bates, J. K.; Brown, N. R.; Buck, E. C.; Dietz, N. L. et al.
Description: Interim report describing progress to develop glassy slag waste forms that support environmental restoration efforts.
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Waste Programs Semiannual Progress Report: April-September 1992

Nuclear Waste Programs Semiannual Progress Report: April-September 1992

Date: May 1994
Creator: Bates, John K.; Bradley, C. R.; Buck, E. C.; Dietz, N. L.; Ebert, William L.; Emery, J. W. et al.
Description: This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April-September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Contributing Partner: UNT Libraries Government Documents Department