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Argonne National Laboratory Chemical Engineering Division Summary Report: July, August, September 1960

Description: 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 ...
Date: October 1961
Creator: Argonne National Laboratory. Chemical Engineering Division.
Partner: UNT Libraries Government Documents Department

Argonne National Laboratory Physics Division Summary Report: September, October 1960

Description: 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.)
Date: October 1961
Creator: Argonne National Laboratory. Physics Division.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: October-December 1975

Description: 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.
Date: 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A. A.
Partner: UNT Libraries Government Documents Department

Physical Parameters in Synthoil Process, Quarterly Report: October-December 1975

Description: 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.
Date: 1976
Creator: Fischer, J.; Lo, R.; Nandi, S.; Fredrickson, D.; Bump, T. R.; Mulcahey, T. P. et al.
Partner: UNT Libraries Government Documents Department

Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: April-June 1976

Description: 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.
Date: 1976?
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A. A.
Partner: UNT Libraries Government Documents Department

Speciation of Radionuclides in Natural Groundwaters, Annual Report: October 1986 through September 1987

Description: Two ultrasensitive laser techniques, laser photoacoustic spectroscopy (LPAS) and laser-induced fluorescence (LIF), are being developed for the detection and speciation of trace levels of actinides in solutions typical of those expected in a high-level waste repository. An LPAS system was set up for these studies. Experiments were carried out to determine the detection limits of plutonium and americium in solution. Concurrently with the LPAS work, LIF studies were carried out on uranyl ion and curium in solution.
Date: February 1988
Creator: Doxtader, M. M.; Beitz, J. V.; Reed, Donald Timothy & Bates, John K.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Chemical Engineering Division Reactor Safety and Physical Properties Studies Annual Report, July 1975-June 1976

Description: 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.
Date: 1976?
Creator: Leibowitz, L.; Blomquist, R. A.; Fink, J. K.; Finn, P. A.; Fischer, D. F.; Green, D. W. et al.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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

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.
Date: 1976?
Creator: Johnson, C. E.; Blackburn, P. E.; Carroll, K.; Fee, D. C.; Fischer, A. K.; Johnson, I. et al.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Chemical Engineering Division Environmental Chemistry Annual Report: July 1975-June 1976

Description: 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.
Date: 1976?
Creator: Cunningham, P. T.; Kumar, R.; Holt, B. D.; Hubble, B. R.; Johnson, S. A.; Nielsen, E. et al.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Physical Parameters in Synthoil Process, Quarterly Report: January-March 1976

Description: 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.
Date: 1976?
Creator: Fischer, J.; Lo, R.; Nandi, S.; Fredrickson, D.; Bump, T. R.; Mulcahey, T. P. et al.
Partner: UNT Libraries Government Documents Department