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 Serial/Series Title: Argonne National Laboratory Reports
Physics Division Annual Review: April 1, 1994-March 31, 1995

Physics Division Annual Review: April 1, 1994-March 31, 1995

Date: August 1995
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.
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Validation of the Generic TRUEX Model Using Data from TRUEX Demonstrations with Actual High-Level Waste

Validation of the Generic TRUEX Model Using Data from TRUEX Demonstrations with Actual High-Level Waste

Date: August 1995
Creator: Regalbuto, M. C.; Aase, S. B. & Vandegrift, G. F.
Description: The Generic TRUEX Model (GTM) was used to simulate three different counter-current flowsheet tests performed using mixer-settlers that had been carried out prior to 1993 in the Chemical Processing Facility, Tokai-works, of the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The feed for the PNC runs was the highly active raffinate from reprocessing of spent fuel from fast breeder reactors. The PNC demonstration runs were planned without using the GTM. Results predicted by the GTM and those obtained experimentally by PNC for the three demonstration runs are compared. Effects of stage efficiency, nitrate complexation, temperature, and equipment type are also included.
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Aqueous Biphasic Extraction of Uranium and Thorium from Contaminated Soils : Final Report

Aqueous Biphasic Extraction of Uranium and Thorium from Contaminated Soils : Final Report

Date: July 1995
Creator: Chaiko, David J.; Gartelmann, J.; Henriksen, J. L.; Krause, T. R.; Deepak; Vojta, Y. et al.
Description: The aqueous biphasic extraction (ABE) process for soil decontamination involves the selective partitioning of solutes and fine particulates between two immiscible aqueous phases. The biphase system is generated by the appropriate combination of a water-soluble polymer (e.g., polyethylene glycol) with an inorganic salt (e.g., sodium carbonate). Selective partitioning results in 99 to 99.5% of the soil being recovered in the cleaned-soil fraction, while only 0.5 to 1% is recovered in the contaminant concentrate. The ABE process is best suited to the recovery of ultrafine, refractory material from the silt and clay fractions of soils. During continuous countercurrent extraction tests with soil samples from the Fernald Environmental Management Project site (Fernald, OH), particulate thorium was extracted and concentrated between 6- and 16-fold, while the uranium concentration was reduced from about 500 mg/kg to about 77 mg/kg. Carbonate leaching alone was able to reduce the uranium concentration only to 146 mg/kg. Preliminary estimates for treatment costs are approximately $160 per ton of dry soil. A detailed flowsheet of the ABE process is provided.
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Extraction of Long-Lived Radionuclides from Caustic Hanford Tank Waste Supernatants

Extraction of Long-Lived Radionuclides from Caustic Hanford Tank Waste Supernatants

Date: July 1995
Creator: Chaiko, David J.; Mertz, C. J.; Vojta, Y.; Henriksen, J. L.; Neff, R. & Takeuchi, M.
Description: A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as Tc-99 and I-129, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO₄⁻ and I⁻ are selectively transferred to the less dense PEG-rich aqueous phase. The partition coefficients for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrite, and carbonate, are all less than one. The partition coefficients for pertechnetate ranged from 12 to 50, depending on the choice of waste simulant and temperature. The partition coefficient for iodide was about 5, while that of iodate was about 0.25. Irradiation of the PEG phase with gamma-ray doses up to 20 Mrad had no detectable effect on the partition coefficients. The most selective extraction systems examined were those based on PPGs, which exhibited separation factors in excess of 3000 between TcO₄⁻ and NO₃⁻/NO₂⁻. An advantage of the PPG-based system is minimization of secondary waste production. These studies also highlighted the need for exercising great care in extrapolating the partitioning behavior ...
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Information Exchange within the U.S. Department of Energy Pollution Prevention Community

Information Exchange within the U.S. Department of Energy Pollution Prevention Community

Date: July 1995
Creator: Thuot, James R.
Description: Improving Pollution Prevention and Waste Minimization Program (PP/WMIN) technologies, actions, and culture could be an important cost-cutting step for the US Department of Energy (DOE). Communicating ideas, concepts, process changes, and achievements is essential for the success of this program. The need to openly communicate ideas and concepts in a cost-effective manner is essential in an organization that has such diverse components as research and development, weapons production, and power generation. This approach is in contrast to the historic DOE culture developed within the cold war period in which compartmentalization, independence, and secrecy were stressed. DOE has now recognized that for any pollution prevention program to be successful, the many diverse elements of the organization must share information. Avenues for such information exchange are examined in this report.
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Nonlinear Dynamics of a Stack/Cable System

Nonlinear Dynamics of a Stack/Cable System

Date: July 1995
Creator: Cai, Y. & Chen, Shoei-Sheng
Description: In this study, we developed a coupled model of wind-induced vibration of a stack, based on an unsteady-flow theory and nonlinear dynamics of the stack's heavy elastic suspended cables. Numerical analysis was performed to identify excitation mechanisms. The stack was found to be excited by vortex shedding. Once lock-in resonance occurred, the cables were excited by the transverse motion of the stack. Large-amplitude oscillations of the cables were due to parametric resonance. Appropriate techniques have been proposed to alleviate the vibration problem.
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Technology Development Goals for Automotive Fuel Cell Power Systems

Technology Development Goals for Automotive Fuel Cell Power Systems

Date: July 1995
Creator: Thomas, C. E. & James, Brian D.
Description: Directed Technologies, Inc. has previously submitted a detailed technical assessment and concept design for a mid-size, five-passenger fuel cell electric vehicle (FCEV), under contract to Argonne National Laboratory. As a supplement to that contract, DTI has reviewed the literature and conducted a preliminary evaluation of two energy carriers for the FCEV: hydrogen and methanol. This report compares the estimated fuel efficiency, cost of producing and delivering the fuel, and the resultant life cycle costs of the FCEV when fueled directly by hydrogen and when fueled by methanol with on-board reforming to produce the required hydrogen-rich gas for the fuel cell. This work will be supplemented and expanded under the Ford contract with the Department of Energy to develop the FCEV and its fuel infrastructure.
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ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1993 - September 1994

ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1993 - September 1994

Date: June 1995
Creator: Bates, John K.
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.
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Chemical Technology Division Annual Technical Report: 1994

Chemical Technology Division Annual Technical Report: 1994

Date: June 1995
Creator: Argonne National Laboratory. Chemical Technology Division.
Description: Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1994. These included electrochemical technology; fossil energy research; hazardous waste research; nuclear waste programs; separation science and technology; electrometallurgical technology; actinide recovery; applied physical chemistry; basic chemistry research; analytical chemistry.
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Argonne National Laboratory-East Site Environmental Report for Calendar Year 1994

Argonne National Laboratory-East Site Environmental Report for Calendar Year 1994

Date: May 1995
Creator: Golchert, N. W. & Kolzow, R. G.
Description: This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed.
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Radiolysis and Hydrolysis of Magnetically Assisted Chemical Separation Particles

Radiolysis and Hydrolysis of Magnetically Assisted Chemical Separation Particles

Date: May 1995
Creator: Buchholz, B. A.; Nuñez, Luis & Vandegrift, G. F.
Description: This report discusses experiments with various ways to conduct a magnetically assisted chemical separation (MACS) process, designed to separate transuranic (TRU) elements out of high-level waste (HLW) or TRU waste.
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Surveillance of Site A and Plot M : Report for 1994

Surveillance of Site A and Plot M : Report for 1994

Date: May 1995
Creator: Golchert, N. W.
Description: The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for 1994 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment.
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User Interface Program for Secure Electronic Tags

User Interface Program for Secure Electronic Tags

Date: May 1995
Creator: Cai, Y.; Koehl, E. R.; Carlson, R. D. & Raptis, A. C.
Description: This report summarizes and documents the efforts of Argonne National Laboratory (ANL) in developing a secure tag communication user interface program comprising a tag monitor and a communication tool. This program can perform the same functions as the software that was developed at the Lawrence Livermore National Laboratory (LLNL), but it is enhanced with a user-friendly screen. It represents the first step in updating the TRANSCOM Tracking System (TRANSCOM) by incorporating a tag communication screen menu into the main menu of the TRANSCOM user program. A working version of TRANSCOM, enhanced with ANL secure-tag graphics, will strongly support the Department of Energy Warhead Dismantlement/Special Nuclear Materials Control initiatives. It will allow commercial satellite tracking of the movements and operational activities of treaty-limited items and transportation vehicles throughout Europe and the former USSR, as well as the continental US.
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Application of NMR Spectroscopy and Multidimensional Imaging to the Gelcasting Process and in-situ Real-Time Monitoring of Cross-Linking Polyacrylamide Gels

Application of NMR Spectroscopy and Multidimensional Imaging to the Gelcasting Process and in-situ Real-Time Monitoring of Cross-Linking Polyacrylamide Gels

Date: April 1995
Creator: Ahuja, S.; Dieckman, S. L.; Gopalsami, Nachappa; Raptis, A. C. & Omatete, Oritsegbemi O.
Description: In the gelcasting process, a slurry of ceramic powder in a solution of organic monomers is cast in a mold. The process is different from injection molding in that it separates mold-filling from setting during conversion of the ceramic slurry to a formed green part. In this work, NMR spectroscopy and imaging have been conducted for in-situ monitoring of the gelation process and for mapping the polymerization. ¹H nuclear magnetic resonance spectra have been obtained during polymerization of a premix of soluble reactive methacrylamide (monomer) and N, N'-methylene bisacrylamide (cross-linking molecules). The premix was polymerized by adding ammonium persulfate (initiator) and tetramethyl-ethylene-diamine (accelerator) to form long-chain, cross-linked polymers. The time-varying spin-lattice relaxation times T₁ during polymerization have been studied at 25 and 35 C, and the variation of spectra and T₁ with respect to extent of polymerization has been determined. To verify homogeneous polymerization, multidimensional NMR imaging was utilized for in-situ monitoring of the process. The intensities from the images are modeled and the correspondence shows a direct extraction of T₁ data from the images.
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Dynamic Stability Experiment of Maglev Systems

Dynamic Stability Experiment of Maglev Systems

Date: April 1995
Creator: Cai, Y.; Rote, D. M.; Mulcahy, T. M.; Wang, Z.; Chen, Shoei-Sheng & Zhu, S.
Description: This report summarizes the research performed on Maglev vehicle dynamic stability at Argonne National Laboratory during the past few years. It also documents magnetic-force data obtained from both measurements and calculations. Because dynamic instability is not acceptable for any commercial Maglev system, it is important to consider this phenomenon in the development of all Maglev systems. This report presents dynamic stability experiments on Maglev systems and compares their numerical simulation with predictions calculated by a nonlinear dynamic computer code. Instabilities of an electrodynamic system (EDS)-type vehicle model were obtained from both experimental observations and computer simulations for a five-degree-of-freedom Maglev vehicle moving on a guideway consisting of double L-shaped aluminum segments attached to a rotating wheel. The experimental and theoretical analyses developed in this study identify basic stability characteristics and future research needs of Maglev systems.
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IPNS Upgrade: a Feasibility Study

IPNS Upgrade: a Feasibility Study

Date: April 1995
Creator: Argonne National Laboratory
Description: Many of Argonne National Laboratory`s (ANL`s) scientific staff members were very active in R & D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R & D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL`s Intense Pulsed Neutron Source (IPNS) to 1 MW by ...
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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.
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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.
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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.
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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 ...
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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.
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