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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
Argonne National Laboratory Chemical Engineering Division Summary Report: July, August, September 1960
9 : : 7 : 7 9 : 5 5 ? 5 9 G -- 8 ; 8 ; = -activity levels of the melt-refining process for EBR-II core fuel was completed. An experiment was also completed on the evolution of fission- product krypton and xenon from an irradiated fuel pim as it was heat to a temperature above the melting point. In tests of alternate materials for use in a meltrefining furnace, a fibrous potassium titanate grain retainer was found to be a very effective heat insulator, but to have less strength than nigid Fibenfrax retainers. The skull remaining in the zirconia crucible after a meltrefining operation must be processed to recover, as partially purified metal, the fissionable material for return to the fuel cycle. Several essentially quantitative reductions of uranium dioxide and skull oxides were achieved in times of less than 8 hr at 800 deg C in dilute magnesium-zinc solutions and in magnesium containing a small percentage (0.5 to 2) of sodium as a wetting agent. Data and equations for solubilities of other elements in liquid cadmium are included. The partition coefficients of a numbsr of representative fissile and fission product elements between the two immiscible liquids, lead and zinc, at about 735 deg C were measured. The free energy of formation of the uraniumthallium intermetallic compound UTl/sub 3/ was measured, using a galvanic cell method. Galvanic cell measurements with the cerium-zinc system at 443 to 742 deg C were also made. The determination of the heat of formation of zirconium tetrafluoride by combustions of zirconium in fluonine was completed. A valus of -372.44 kcal/mole was obtained for the heat of formation of molybdenum hexafluoride. Calorimetric oombustions of boron in fluorine are being continued. Exploratory combustions of magnesium, aluminum, zinc, and cadmium are being carried out. Fuel Cycle Application of Volatility and Fluidization Techniques. Investigation of the stoichiometry of the reaction of plutonium hexafluoride with sulfur tetrafluonide was completed. The investigation of the stoichiometry of the reactions of sulfur tetrailuoride with uranium tnioxide, uranium dioxide, uranyl fluoride, and U/sub 3/O/sub 8/ was also completed. Radiation decomposition of plutoniuna hexafluonide in the presence of uranium hexafluoride at 2.6% per day, was found to be very similar to the value obtained for plutonium hexafluonide alone. In terms of wt.% hydrogen chloride, the solubility of hydrogen chloride in liquid hydrogen fluoride is 0.7 at -38 deg C and 2.4 at -78 deg C. An investigation of the corrosive effsct of hydrogen fluoride-hydrogen chloride gas mixtures on A-nickel has been initiated. Additionai studies of metal fluoninations were concerned with the mechanisms of the nickel-fluonine and nickel-oxygen reactions. Work continued on engineering-scale studies of the Direct Fluorination Process applied to dense uranium dioxide pellet fuel. Decladding runs were made to investigate the effect of close packing of fuel elements on operation of the fluid-bed reactor. Mock-up tests of heat transfer from the surface of fixed packing submenged in a fluid bed were made to determine the effects of bed height and gas velocity. A final dissolution was performed in a series of dissolutions of synthetic fuel assemblies to demonstrate operation of the graphite pilot-plant dissolver. Examination of the walls of the graphite dissolver showed the expected presence of fused salt in the ninddle of the lampblack insulating zone. A fused-salt charge was allowed to freeze in the dissolver to determine the effect that this would have on dissolver components. Extsnsive damage to internal graphite downlines and heaters was found. Reactor Safety. In the continued study of the ignition of uranium it was confirmed that an aggregate or array of pieces ignites at a considerably lower temperature than an individual pices of the same specific area. Continued studies of the effects of halogenated hydrocar digital.library.unt.edu/ark:/67531/metadc864532/
Argonne National Laboratory Physics Division Summary Report: September, October 1960
The use and operation of the Van de Graaff generator are summarized for the period from January 1 to June 30, 1960. Molecular beam study final results are given for Mn/sup 56/, and progress on the new atomic-beam machine is reported to date. A preliminary investigation was made of the neutron total cross section of cobalt. Results are presented. The decomposition of trichlorobromomethane by the isomeric transition of 4.4-hr Br/sup 80m/ and to 1000 deg F. /sup -/, decay of 35.9-hr Br/sup 82/ was studied. The fragmnentation patterns initiated by the two nuclear transitions differ markedly, the one caused by the isomeric transition was dominated by spectra of multiply-charged atomic species, whereas the pattern due to Br/sup 82/ was entirely made up of singlycharged products. An investigition of nondiagonal matrix elements arising in a shell-model treatment of a deformed nucleus showed that their neglect in determining the degree of deformation does not lead to serious error. A previous statement, in a study of collective effects and the shell model, about K = 0 bands in odd-odd nuclei is corrected. The effect of residual interactions is calculated, and the result is applied to Ho/sup 166/. (For preceding period see ANL-6190.) (W.D.M.) digital.library.unt.edu/ark:/67531/metadc870783/
Argonne National Laboratory Sodium Technology Quarterly Report: January, February, March 1970
No Description digital.library.unt.edu/ark:/67531/metadc870405/
Argonne National Laboratory Sodium Technology Quarterly Report: July, August, September 1970
No Description digital.library.unt.edu/ark:/67531/metadc869197/
Uses of Advanced Pulsed Neutron Sources. Report of a Workshop Held at Argonne National Laboratory, October 21-24, 1975
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. digital.library.unt.edu/ark:/67531/metadc282652/
Ion Replacement Program Annual Report: 1993
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. digital.library.unt.edu/ark:/67531/metadc283082/
Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois
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. digital.library.unt.edu/ark:/67531/metadc283282/
Separation Science and Technology Semiannual Progress Report: April - September 1992
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. digital.library.unt.edu/ark:/67531/metadc283101/
Division of Biological and Medical Research Annual Report 1980
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. digital.library.unt.edu/ark:/67531/metadc283316/
Chemical Engineering Division Reactor Safety and Physical Properties Studies Annual Report, July 1975-June 1976
A report of the work on Reactor Safety and Physical Property Studies performed in the Chemical Engineering Division at Argonne National Laboratory is given for the period July 1975-June 1976. digital.library.unt.edu/ark:/67531/metadc282906/
High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: July-September 1976
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. digital.library.unt.edu/ark:/67531/metadc282904/
Chemical Engineering Division Physical Inorganic Chemistry Annual Report: July 1975-June 1976
Various aspects of physical inorganic chemistry were investigated and are summarized in this report. digital.library.unt.edu/ark:/67531/metadc282907/
Laboratory Support for in situ Gasification Reaction Kinetics. Quarterly Report, October-December 1976
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. digital.library.unt.edu/ark:/67531/metadc282944/
Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282937/
Chemical Engineering Division Fuels and Materials Chemistry Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282909/
Chemical Engineering Division Fast-Neutron Dosimetry, Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282910/
Plutonium Calorimetry and SNM Holdup Measurements, Progress Report: March 1976-August 1976
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. digital.library.unt.edu/ark:/67531/metadc282945/
Physical Research on Liquid-Metal Systems Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282912/
Chemical Engineering Division Thermochemical Studies Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282908/
High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: October-December 1976
Quarterly report on batteries being developed for electric-vehicle propulsion and for stationary energy storage applications. digital.library.unt.edu/ark:/67531/metadc282954/
Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976
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. digital.library.unt.edu/ark:/67531/metadc282911/
Advanced Evaporator Technology Progress Report FY 1992
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. digital.library.unt.edu/ark:/67531/metadc283090/
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1990 - September 1991
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. digital.library.unt.edu/ark:/67531/metadc283096/
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992
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. digital.library.unt.edu/ark:/67531/metadc283097/
Applied Physical Chemistry Progress Report, October 1991 - September 1992
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. digital.library.unt.edu/ark:/67531/metadc283081/
Land Reclamation Program, Annual Report: July 1975-July 1976
The Land Reclamation Program was initiated at Argonne National Lab. in June, 1975, to address the need for coordinated applied and basic research into the environmental problems associated with utilization of coal, one of the nation's most abundant energy forms. digital.library.unt.edu/ark:/67531/metadc282688/
High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: January-March 1976
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. digital.library.unt.edu/ark:/67531/metadc282679/
Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: January-March 1976
This effort is being directed toward support studies for the national endeavor on in situ coal gasification. This task involves the investigation of reaction-controlling variables and product distributions for the gasification of both coals and chars utilizing steam and oxygen. Included in this task is the investigation of the effects of using brackish water as the water supply. The high-pressure char gasification system has been received from the manufacturer and is currently undergoing testing. The types of experiments that would be most useful in their studies have been discussed with two of the three laboratories carrying out field tests of in-situ gasification. digital.library.unt.edu/ark:/67531/metadc282699/
Physical Parameters in Synthoil Process, Quarterly Report: January-March 1976
This work is being done in support of the development of processes for converting coal to liquid fuel of low sulfur content, suitable for use in power production. Most of the effort is intended to produce information applicable to the SYNTHOIL Process. In the SYNTHOIL Process for converting coal to a low-sulfur fuel oil, coal is liquefied and hydro-desulfurized in a turbulent-flow, catalytic packed-bed reactor. A slurry of coal in recycled oil is reacted with hydrogen at 450 degrees C and 2,000 to 4,000 psi in the presence of Co-MoSiO2-Al2O3 catalyst. The turbulent flow of fluid prevents the coal's mineral matter from settling and plugging the reactor. The gross liquid products are centrifuged to remove the unreacted solids. The centrifuged liquid product is a low-S, low-ash fuel. The following four tasks are included: (1) heat of reaction of hydrogen with coal slurries; (2) heat transfer coefficient; (3) additives to facilitate separation of solids from liquids; and (4) catalyst testing. These are now in the planning stage of development. digital.library.unt.edu/ark:/67531/metadc282694/
Radiological and Environmental Research Division Annual Report: Part 1, Fundamental Molecular Physics and Chemistry October 1976-September 1977
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to molecular physics and chemistry. This report discusses studies on electron collisions with molecules, photo-absorption and its consequences such as photo-electron emission, and pertinent theories. digital.library.unt.edu/ark:/67531/metadc283235/
Radiological and Environmental Research Division Annual Report: Part 4, Atmospheric Physics, January-December 1977
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to atmospheric physics. This report discuses programs in air-water heat transfer and on fog formation on cooling ponds, dispersion characteristics in the wakes of buildings and in coastal regimes and measurements of pollutant fluxes to water surfaces. digital.library.unt.edu/ark:/67531/metadc283240/
Johnson Controls Inc. Battery Division Annual Report, 1985: Research, Development and Demonstration of Lead-Acid Batteries for Electric Vehicle Propulsion
Report on research and development of the lead-acid battery for electric vehicle propulsion, focusing on continuing development on the forced electrolyte flow-through concept with some work on the composite, plastic/lead grid. digital.library.unt.edu/ark:/67531/metadc282783/
Dynamic Behavior of Reacting Gas Jets Submerged in Liquids: a Photographic Study : Annual Report for the Period May 1, 1985 - May 1, 1986
A photographic study of a hydrogen chloride gas jet reacting in an aqueous solution of ammonia was conducted. The high-speed motion pictures taken revealed that the behavior of the reacting gas jet was highly dynamic and complex. The gaseous jet penetration (''plume'') was not stationary, but underwent a change in shape and size with time, which appeared to be periodic or cyclic. Certain observations made, including a high-pitched sound, exhibited a striking similarity to the so-called ''singing flame'' phenomenon. Such dynamic plume behavior is attributed to the vaporization of the bath liquid due to reaction heat release. The plume length measurements for large concentrations of ammonia seem to confirm the prediction that when the extent of vaporization is large, the plume length is mainly determined by the distance required for condensation of the vapor. digital.library.unt.edu/ark:/67531/metadc282798/
Physical Parameters in Synthoil Process, Quarterly Report: October-December 1975
This work is being done in support of the development of processes for converting coal to liquid fuel of low sulfur content, suitable for use in power production. Most of the effort is intended to produce information applicable to the SYNTHOIL Process. In the SYNTHOIL Process for converting coal to a low-sulfur fuel oil, coal is liquefied and hydro-desulfurized in a turbulent-flow, catalytic packed-bed reactor. A slurry of coal in recycled oil is reacted with hydrogen at 450 degrees C and 2,000 to 4,000 psi in the presence of Co-MoSiO2-Al2O3 catalyst. The turbulent flow of fluid prevents the coal's mineral matter from settling and plugging the reactor. The gross liquid products are centrifuged to remove the unreacted solids. The centrifuged liquid product is a low-S, low-ash fuel. The following four tasks are included: (1) heat of reaction of hydrogen with coal slurries; (2) heat transfer coefficient; (3) additives to facilitate separation of solids from liquids; and (4) catalyst testing. These are now in the planning stage of development. digital.library.unt.edu/ark:/67531/metadc173334/
Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: October-December 1975
This effort is being directed toward support studies for the national endeavor on in situ coal gasification. This task involves the investigation of reaction-controlling variables and product distributions for the gasification of both coals and chars utilizing steam and oxygen. Included in this task is the investigation of the effects of using brackish water as the water supply. The high-pressure char gasification system has been received from the manufacturer and is currently undergoing testing. The types of experiments that would be most useful in their studies have been discussed with two of the three laboratories carrying out field tests of in-situ gasification. digital.library.unt.edu/ark:/67531/metadc173333/
Fuel Cycle Programs, Quarterly Progress Report: January-March 1979
Quarterly 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. digital.library.unt.edu/ark:/67531/metadc283302/
SLIDES: a Program to Draw Slides and Posters
SLIDES is a program which takes text and commands as input and prepares lettered slides and posters. When run on the time-sharing computer, the program can display its output on an interactive graphics terminal; in batch, it can direct its graphical output to a variety of plotters. The program uses DISSPLA graphical subroutines and standard ANL plotter subroutines. This report contains material written for the novice computer user, who should be able to produce useful slides or posters by following the examples. This report also serves as a complete reference for the SLIDES program. digital.library.unt.edu/ark:/67531/metadc282963/
Chemical Engineering Division Environmental Chemistry Annual Report: July 1975-June 1976
The chemistry of airborne particulate matter is being investigated by means of laboratory and field studies. Experiments were conducted using the flow reactor to identify the reaction conditions under which detectable amounts of sulfate particles could be formed under gaseous sulfur dioxide. A procedure was developed for the analysis of acidic and neutral ammonium sulfate in filter-collected samples of atmospheric particulate matter. digital.library.unt.edu/ark:/67531/metadc282913/
Nuclear Waste Programs Semiannual Progress Report: October 1991-March 1992
This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 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. digital.library.unt.edu/ark:/67531/metadc283106/
Nondestructive Characterization Methods for Monolithic Solid Oxide Fuel Cells
Monolithic solid oxide fuel cells (MSOFCS) represent a potential breakthrough in fuel cell technology, provided that reliable fabrication methods can be developed. Fabrication difficulties arise in several steps of the processing: First is the fabrication of uniform thin (305 {mu}m) single-layer and trilayer green tapes (the trilayer tapes of anode/electrolyte/cathode and anode/interconnect/cathode must have similar coefficients of thermal expansion to sinter uniformly and to have the necessary electrochemical properties); Second is the development of fuel and oxidant channels in which residual stresses are likely to develop in the tapes; Third is the fabrication of a "complete" cell for which the bond quality between layers and the quality of the trilayers must be established; and Last, attachment of fuel and oxidant manifolds and verification of seal integrity. The purpose of this report is to assess nondestructive characterization methods that could be developed for application to laboratory, prototype, and full-scale MSOFCs. digital.library.unt.edu/ark:/67531/metadc283136/
Nuclear Waste Programs Semiannual Progress Report: April-September 1992
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. digital.library.unt.edu/ark:/67531/metadc283107/
Separation Science and Technology Semiannual Progress Report
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 October 1991-March 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. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. digital.library.unt.edu/ark:/67531/metadc283100/
Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994
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. digital.library.unt.edu/ark:/67531/metadc283105/
Separation Science and Technology Semiannual Progress Report for October 1992 - March 1993
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. digital.library.unt.edu/ark:/67531/metadc283102/
Radiological and Environmental Research Division Annual Report: Part 3, Ecology, January-December 1977
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology. This report discuses programs to study the role of physical processes involved in transferring pollutants from the combustion of fossil fuels to the water surface, to study the biogeochemical behavior of transuranic elements from the Windscale reprocessing plant, and to study the effects of pollutants from power plants on aquatic organisms in the Great Lakes program. digital.library.unt.edu/ark:/67531/metadc283237/
High-Performance Batteries for Stationary Energy Storage and Electric-Vehicle Propulsion, Progress Report: October 1978-March 1979
This report covers the research, development, and management activities of the programs at Argonne National Laboratory (ANL) and at subcontractors' laboratories on high-temperature batteries during the period October 1978 - March 1979. These batteries are being developed for electric-vehicle propulsion and for stationary energy--storage applications. The present cells, which operate at 400-500 C, are of a vertically oriented, prismatic design with one or more inner positive electrodes of FeS or FeS2, facing electrodes of lithium-aluminum alloy, and molten LiCl-KC1 electrolyte. digital.library.unt.edu/ark:/67531/metadc283299/
Plane-Strain Stress Intensity Factors for Cracked Hexagonal Subassembly Ducts
Plane-strain stress intensity factors for a pressurized hexagonal subassembly duct with a crack in a corner or midflat are presented in convenient graphical form for representative LMFBR hexcan dimensions. Corner-crack calibrations based on several different models of the round hexcan corner are determined first in order to bound the stress intensity factor. A subsequent finite-element analysis of a uniformly pressurized hexcan with a corner crack gives accurate data for the stress intensity factor from which a weight function for this geometry may be constructed. The effects of different numbers of cracks, different locations for cracks, and different loading modes are discussed briefly, and some comments are made on the application of linear elastic fracture mechanics to cracked hexagonal ducts that have suffered a high degree of irradiation embrittlement. digital.library.unt.edu/ark:/67531/metadc283256/
Chemical Engineering Division Fuel Cycle Programs Progress Report: January-March, 1978
Quarterly 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. This report includes fuel cycle studies in advanced solvent extraction techniques focused on development of centrifugal contactors for use in Purex processes and dispersion of liquids by explosions. digital.library.unt.edu/ark:/67531/metadc303814/
Addendum to a Proposal for ATLAS: a Precision-Ion Accelerator at Argonne National Laboratory, December 1978
This revised proposal for the construction of the Argonne Tandem-Linac Accelerator System (ATLAS) is in all essentials the same as the proposal originally presented to NUSAC in March 1978. The only differences worth mentioning are the plan to expand the experimental area somewhat more than was originally proposed and an increased cost, brought about principally by inflation. The outline presented is the same (with minor change in wording) as in the original document, reproduced here for the convenience of the reader. digital.library.unt.edu/ark:/67531/metadc303816/
Nondestructive Evaluation Techniques for Silicon Carbide Heat-Exchanger Tubes : Second Annual Report, October 1978-September 1979
This report discusses the development of ultrasonic testing, acoustic microscopy, dye-enhanced radiography, holographic interferometry, and infrared scanning techniques for flaw detection in silicon carbide (SiC) heat-exchanger tubing. Both preservice and in-service testing requirements are discussed. An ultrasonic boreside probe and an acoustic microscope stage have been designed for continuous monitoring of SiC tubing. Preliminary results with these acoustic systems are presented. In addition, a novel technique for detecting small surface flaws using holographic interferometry is discussed. Fracture mechanics analysis suggests that detection of flaws on the order of 100 um is necessary to assure good reliability of ceramic heat exchangers. The acoustic and holographic techniques have been shown to be capable of detecting flaws of this size. However, the sensitivity of ultrasonic flaw detection in SiC is affected by the microstructure of the component. The practical considerations involved in the use of these techniques are discussed. digital.library.unt.edu/ark:/67531/metadc283420/
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