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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

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

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

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
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

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

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.
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

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

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.
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 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 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

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.
Partner: UNT Libraries Government Documents Department