UNT Libraries Government Documents Department - 1,233 Matching Results

Search Results

Uses of Advanced Pulsed Neutron Sources. Report of a Workshop Held at Argonne National Laboratory, October 21-24, 1975

Description: This report contains the conclusions that were drawn by nine panels of scientists in the fields of Biology; Chemical Spectroscopy; Chemical Structures of Crystalline Solids; Chemical Structures of Disordered Solids and Inhomogeneous Systems; Dynamics of Solids, Liquids, Glasses, and Gases; Magnetism; Neutron Sources; and Radiation Effects. The nine panel reports describe the applications found in these scientific areas, accompanying them with conceptual instruments designed for the measurements and with calculations to establish feasibility.
Date: 1976?
Creator: Carpenter, S. A.

Ion Replacement Program Annual Report: 1993

Description: Annual report of the Ion Replacement Electrorefining Program at Aronne National Laboratory describing their research and activities. There are three key accomplishments highlighted for the year: (1) identification of a suitable sodium(beta){double_prime}-alumina/molten salt electrolyte system that functions reproducibly at 723 K, (2) actual separation of dysprosium and lanthanum in experiments, and (3) the identification of a metal alloy, Li{sub x}Sb, as an alternative ion replacement electrode.
Date: July 1993
Creator: Tomczuk, Z.

Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois

Description: Papers presented at the third Post-Accident Heat Removal Information Exchange concerning heat distribution and criticality considerations, particulate-bed phenomena, pool heat transfer and melt-front phenomena, behavior of heated concrete and sodium-concrete interactions, design-related studies, gas bubbling and boiling effects, and materials interactions at high temperatures and experimental methods.
Date: 1978?
Creator: Baker, Louis, Jr.

Operational Health Physics Training

Description: This revised publication updates a previous report (ANL-7291) initially published in 1965, entitled Radiation Safety Technician Training Course which was intended to complement on-the-job monitoring training for Health Physics Technicians. Sections include basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of alpha, beta, gamma, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units).
Date: June 1992
Creator: Moe, H. J. & Vallario, Edward J.

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

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.
Date: September 1994
Creator: Vandegrift, G. F.

Division of Biological and Medical Research Annual Report 1980

Description: The research during 1980 in the Division of Biological and Medical Research, Argonne National Laboratory, is summarized. Research related to nuclear energy includes the delineation, in the6 eagle, of the responses to continuous low level Co gamma radiation and the development of cellular indicators of preclinical phases of leukemia; comparison of lifetime effects in mice of low level neutron and Co gamma radiation.
Date: August 1981
Creator: Argonne National Laboratory. Division of Biological and Medical Research.

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

Description: Quarterly report describing the research and management efforts of the program at ANL on lithium-aluminum/metal sulfide batteries. These batteries are being developed for electric-vehicle propulsion and for stationary energy storage applications.
Date: December 1976
Creator: Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.

Laboratory Support for in situ Gasification Reaction Kinetics. Quarterly Report, October-December 1976

Description: This work, which is part of the ANL energy program for ERDA, is directed toward studies for the national endeavor on in situ coal gasification. The objective of this work is to determine the reaction-controlling variables and reaction kinetics for gasification of chars resulting when coal is pyrolyzed in underground gasification. The reactions to be studied include steam-char, carbon dioxide-char, hydrogen-char, and water gas shift reaction. Discussed in this report are the effects on the reactivity of chars of pyrolysis in simulated gasification product gas rather than pure nitrogen. In addition, further investigations of the water gas shift reaction and methanation reaction are discussed.
Date: January 1977
Creator: Fischer, J.

Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976

Description: The hydrogen permeabilities of selected metals, alloys, and multiplex preparations that are of interest to fusion reactor technology are being characterized. A high-vacuum hydrogen-permeation apparatus has been constructed for this purpose. A program of studies has been initiated to develop design details for the tritium-handling systems of near-term fusion reactors. This program has resulted in a better definition of reactor-fuel-cycle and enrichment requirements and has helped to identify major research and development problems in the tritium-handling area. The design and construction of a 50-gallon lithium-processing test loop (LPTL) is well under way. Studies in support of this project are providing important guidance in the selection of hardware for the LPTL and in the design of a molten-salt processing test section.
Date: 1976?
Creator: Maroni, V. A.; Calaway, W. F.; Misra, B.; Van Deventer, E. H.; Wegton, J. R.; Yonco, R. M. et al.

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

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.
Date: 1976?
Creator: Heinrich, R. R.; Greenwood, L. R.; Kennerley, R. J.; Chellew, N. R.; Popek, R. J.; Malewicki, Russell et al.

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

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 neutrons. In addition, the use of infrared imaging devices to measure small temperature differences is considered for locating large amounts of plutonium holdup and also for performing fast attribute checks for fabricated fuel elements.
Date: February 1977
Creator: Brumbach, S. B.; Finkbeiner, A. M.; Lewis, R. N. & Perry, R. B.

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

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.
Date: January 1977
Creator: Moroni, V. A.; Veleckis, Ewald; Calaway, W. F.; Yonco, R. M.; Cafasso, F. A. & Burris, L.

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

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.
Date: 1976?
Creator: O'Hare, P. A. G.; Johnson, G. K.; Ader, M.; Hubbard, W. N.; Fredrickson, D.; Cafasso, F. A. et al.

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

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.
Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.

Advanced Evaporator Technology Progress Report FY 1992

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 at Argonne-East in FY 1993 to process low-level radioactive waste generated throughout the laboratory. They will also provide operating data from a full-sized evaporator processing radioactive solutions. Details on these evaporators are included in this report.
Date: January 1995
Creator: Chamberlain, D. B.

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

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.
Date: March 1992
Creator: Bates, John K.

Applied Physical Chemistry Progress Report, October 1991 - September 1992

Description: This document reports on the work done in applied physical chemistry at the Chemical Technology Division (CMT), Argonne National Laboratory (ANL), in the period October 1991 through September 1992. this work includes research into the process that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor under development at ANL, and the properties of candidate tritium breeding materials in environments simulating those of fusion energy systems.
Date: December 1993
Creator: Johnson, C. E.

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

Description: Quarterly report describing the research and management effort of Argonne National Laboratory's program on lithium/metal sulfide batteries during the period January-March 1976. These batteries are being developed for energy storage on utility networks and for electric-vehicle propulsion. The present cells are vertically oriented, piismatic cells with a central positive electrode of FeS or FeS; and two facing negative electrodes of lithium-aluminum alloy, and an electrolyte of molten LiCl-KC1. The cell operating temperature is 400-450C.
Date: May 1976
Creator: Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.