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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
Chemical Engineering Division Fuels and Materials Chemistry Annual Report: July 1975-June 1976

Chemical Engineering Division Fuels and Materials Chemistry Annual Report: July 1975-June 1976

Date: 1976?
Creator: Johnson, C. E.; Blackburn, P. E.; Carroll, K.; Fee, D. C.; Fischer, A. K.; Johnson, I. et al.
Description: Annual report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
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Chemical Engineering Division Fast-Neutron Dosimetry, Annual Report: July 1975-June 1976

Chemical Engineering Division Fast-Neutron Dosimetry, Annual Report: July 1975-June 1976

Date: 1976?
Creator: Heinrich, R. R.; Greenwood, L. R.; Kennerley, R. J.; Chellew, N. R.; Popek, R. J.; Malewicki, Russell et al.
Description: One of the objectives of the Dosimetry and Damage Analysis Center is to provide standardized dosimetry technology for materials-study programs within the ERDA Division of Magnetic Fusion Energy. Current efforts have included characterization of neutron environments in terms of fluence and spectral distribution for materials experiments conducted at the Lawrence Livermore Laboratory's (LLL) Rotating Target Neutron Source and at the LLL-Davis Cyclograaff. Environment characterization efforts at Brookhaven National Laboratory's High Flux Beam Reactor and those pertaining to an enriched-uranium converter for the ANL CP-5 reactor are also described. The capability of calculating material radiation damage parameters associated with these neutron environments is demonstrated. Average fission yields determined from two fast-neutron irradiations and one thermal-neutron irradiation are compiled for laboratories participating in the inter-laboratory Reaction Rate program. These results are in excellent agreement with literature values. Progress on the development of boron-10 and lithium-6-loaded liquid scintillation detectors for detecting very low intensity neutrons is presented. Material purification tests and performance tests of scintillation mixtures are described.
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Plutonium Calorimetry and SNM Holdup Measurements, Progress Report: March 1976-August 1976

Plutonium Calorimetry and SNM Holdup Measurements, Progress Report: March 1976-August 1976

Date: February 1977
Creator: Brumbach, S. B.; Finkbeiner, A. M.; Lewis, R. N. & Perry, R. B.
Description: The calorimetric instrumentation developed at Argonne National Laboratory (ANL) for making nondestructive measurements of the plutonium content of fuel rods is discussed. Measurements with these instruments are relatively fast (i.e., 15 to 20 minutes) when compared to the several hours usually required with more conventional calorimeters and for this reason are called ''fast-response.'' Most of the discussion concerns the One-Meter and the Four-Meter Fuel-Rod Calorimeters and the Analytical Small-Sample Calorimeter. However, to provide some background and continuity where needed, a small amount of discussion is devoted to the three earlier calorimeters which have been described previously in the literature. A brief review is presented of the literature on plutonium holdup measurements. The use of gamma-ray techniques for holdup measurements is discussed and results are given for the determination of sample thickness using the ratio of intensities of high- and low-energy gamma rays. The measurements cover the plutonium metal thickness range from 0.001 to 0.120 inches. The design of a gamma-ray collimator with 37 parallel holes is also discussed. Neutron-counting experiments using BF3 proportional counters embedded in two polyethylene slabs are described. This detector configuration is characterized for its sensitivity to sample and background plutonium, counting both coincidence (fission) and total ...
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Physical Research on Liquid-Metal Systems Annual Report: July 1975-June 1976

Physical Research on Liquid-Metal Systems Annual Report: July 1975-June 1976

Date: January 1977
Creator: Moroni, V. A.; Veleckis, Ewald; Calaway, W. F.; Yonco, R. M.; Cafasso, F. A. & Burris, L.
Description: Physicochemical and thermodynamic studies of liquid-lithium-containing systems have continued. Pressure-composition isotherms for the lithium-hydrogen system measured by a gravimetric technique are found to be in reasonably good agreement with earlier tensimetric results. Plateau-pressure studies of the lithium-hydrogen, lithium-deuterium, and lithium-tritium systems have been made at temperatures above and below the monotectic. The observed isotope effects were found to be near the predicted values. Measurements of the solubility of the lithium-deuterium in liquid lithium gave results in good agreement with prior data for the solubility of lithium-hydrogen in lithium and confirmed that the limits on cold trapping of lithium hydrides from lithium are too high for protected fusion reactor applications. Determination of the solubility of lithium dioxide in liquid lithium is nearing completion. Solubility values measured to date are slightly lower than, but in the range of, prior measurements.
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Chemical Engineering Division Thermochemical Studies Annual Report: July 1975-June 1976

Chemical Engineering Division Thermochemical Studies Annual Report: July 1975-June 1976

Date: 1976?
Creator: O'Hare, P. A. G.; Johnson, G. K.; Ader, M.; Hubbard, W. N.; Fredrickson, D.; Cafasso, F. A. et al.
Description: Standard enthalpies of formation at 298.15 K are reported for MgUO4, CaUO4, BaUO4, VF3, and PrF3 based on solution and fluorine bomb calorimetric measurements. High-temperature enthalpy increments have been determined for MgUO4 by drop calorimetry. Preliminary work on gamma -UO3 and beta-LiAl is described.
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High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: October-December 1976

High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: October-December 1976

Date: April 1977
Creator: Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.
Description: Quarterly report on batteries being developed for electric-vehicle propulsion and for stationary energy storage applications.
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Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.
Description: The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measure tritium specific activities and to test the model of an operating LMFBR. The second part of the program is focused in two areas: 91) on-reactor-site conversion of commercial-grade sodium and (2) requalifying sodium from decommissioned reactors for reuse in future LMFBRs.
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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 ...
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ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1990 - September 1991

ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1990 - September 1991

Date: March 1992
Creator: Bates, John K.
Description: A program has been established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are likely to affect waste glass reaction during repository disposal, with emphasis on an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
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ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992

ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992

Date: May 1993
Creator: Bates, John K.
Description: 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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