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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 testin… more
Date: 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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… more
Date: 1976
Creator: Fischer, J.; Lo, R.; Nandi, S.; Fredrickson, D.; Bump, T. R.; Mulcahey, T. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculations on U235 Fission Product Decay Chains

Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Date: May 1952
Creator: Faller, I. L.; Chapman, T. S. & West, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IsotopesProduction Reactor: Summary of Complete Design

Description: Report describing an Isotope Production Reactor, which may be of interest to industrial groups studying the possibilities of entering the radioactive isotopes production field. Detailed drawings and specifications for the construction of the reactor are included.
Date: 1955
Creator: Winkleblack, R. K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Description: Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity as a Function of Irradiation Time in Thermal Reactors

Description: Equations governing the variation of U235. U238, Pu239, Pu240, and Pu241 have been derived and their solutions plotted as a function of irradiation time. The initial U235 content of the uranium was varied from 0.5% to 2.0%. The range of conversion ratios was from 0.5 to 1.2. The irradiation was from 0 to 20,000 mwd/ton of fuel. Since a range of initial conversion ratios is associated with each value of enrichment, a solution results in a family of curves for each isotope, and, since the range o… more
Date: December 1953
Creator: Carter, J. C. & West, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication and Properties of Extruded Silver-Cadmium Control Rods

Description: The production of cross-type control rods having a span of 4-7/8 in., and an arm thickness of 1/8 in., was studied. Extrusion techniques were developed for producing cross-type control rods from each of two alloys; one containing 75% silver-25% cadmium, and the other containing 67% silver-30% cadmium-3% copper. Fabrication of the extruded crosses into clad control rods for the Mark I naval reactor was attempted. A set of unclad control rods for the Zero Power Reactor was produced. The effect of… more
Date: January 1952
Creator: Dwight, Austin E. (Austin Elbert), 1919-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: December 15, 1953
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report January, February, and March, 1954

Description: Progress is reported on (1) direct cycle boiling reactor studies, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) fluidization studies, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: May 1, 1954
Creator: Lawroski, Stephen; Rodger, W. A. & Vogel, R. C., 1928-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Hazard Summary Report on the Boiling Experiment Reactor (BER)

Description: Experiments performed by the Laboratory with the Borax Reactor at the National Reactor Testing Station have demonstrated that a boiling reactor possesses inherent safety characteristics which have not previously been included in the estimation of reactor hazards. Other operating characteristics of Borax were also sufficiently attractive to justify the development of boiling reactors for package power and central station power plant applications. Accordingly, a proposal was made to the Atomic En… more
Date: May 1954
Creator: West, J. M.; Anderson, G. A.; Dietrich, J. R.; Harrer, Joseph M.; Jameson, A. S. & Untermyer, Samuel, 1912-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report October, November, and December 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: December 31, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Soluble Poisons in Reactor Control

Description: Theoretical and experimental investigations of the use of soluble poisons (neutron absorbers) to supplement mechanical control rods are summarized. Experimental evaluation of poisons of interest includes in-pile and out-of-pile tests simulating anticipated reactor operating conditions. Other phases of the investigation included methods of poison injection, removal, and cleanup of poison-diluted reactor systems, as well as studies to evaluate possible application of soluble poison control in exi… more
Date: November 1955
Creator: Breden, Calvin Rudolph, 1901-; Brown, W. S. & Sivetz, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dimensional Stability of Uranium Powder Compacts Upon Thermal Cycling

Description: Thermal cycling tests on uranium have shown that the dimensional changes that occur on cycling in the alpha range are directly related to both the texture of the material and its grain size: cold rolled rods generally elongate in the direction of rolling, while the same rods, after a beta-treatment, grow at rates several orders of magnitude lower. This considerable improvement by beta-treatment has been attributed to the texture randomization accompanying the heat-treatment. In the course of th… more
Date: November 30, 1953
Creator: Mayfield, R. M.; Zegler, S. T. & Chiswik, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Differential Thermal Analysis of Irradiated Diamond and Silicon Carbide

Description: It was demonstrated by differential thermal analysis (DTA) that: 1. Catastrophic amounts of energy can be stored in diamond. 2. Even at low irradiations, the release takes place over serval hundred degrees, indicating a spectrum of activation energies. 3. At higher irradiations, the stored energy release is considerably less than the increased energy contents and seems not to have been completely released even at the highest temperatures reached. 4. There is some indication of an increased heat… more
Date: December 1, 1954
Creator: Primak, William, 1917-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1953

Description: Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: January 1, 1954
Creator: Lawroski, Stephen & Stevenson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Factors Which Affect Formation and Deposition of Transport Corrosion Products in High-Temperature Recirculating Water Loops

Description: Deposits of corrosion products form on heat transfer surfaces and in radiation flux zones at temperatures around 500F in stainless steel systems operating with circulating water. The report considers the possible harmful effects of such deposits on heat transfer and fluid flow, as well as factors involved in the origin of these corrosion products and in the mechanisms of deposition. The prevention of deposition by chemical, mechanical, and electrostatic methods is discussed.
Date: December 1953
Creator: Wohlberg, C. & Kleimola, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Fuel Element Parts and Assemblies by the Radiographic Method

Description: Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be under… more
Date: July 1, 1954
Creator: VanderLaan, Robert H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report January, February, and March 1954

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: March 31, 1954
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Regeneration Factor as a Function of Time in a Th232 - U235 Thermal Reactor

Description: This technical report is concerned with a theoretical investigation of the variation of the regeneration factor [gamma] in a Th232 - U235 thermal reactor. The abundances of the significant isotopes in the thorium-uranium cycle have been derived as a function of irradiation time at constant reactor power. The change in [gamma] as a function of irradiation time at constant power was calculated for combinations of enrichment and resonance escape probability considered likely to exist in a thermal … more
Date: September 1954
Creator: Carter, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Production Analysis - Graphical Method

Description: In the a study of plutonium production, the analytical solutions of the various isotope production equations are difficult and time consuming when spatial variation of the flux is considered. In an effort to reduce the time and labor required to determine the integrated production of a given thermal reactor, a graphical method of analysis is presented. The method is based on the assumption that the reactor may be divided into a relatively small number of regions such that the flux in each of th… more
Date: January 1954
Creator: Mumm, J. F. & Templin L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Zirconium Clad Uranium Plates for Reactor Fuel

Description: In this investigation a method has been developed for production of Zrclad uranium plate based upon previous investigations at Argonne and Oak Ridge National Laboratories, and preliminary in investigations in their present work. The present preliminary investigations included experimental studies of the effect of interface atmosphere upon roll bonding and led to the conclusion that thin layers of air between bonding surfaces could be tolerated.
Date: unknown
Creator: Lawless, J. J.; Bean, C. H.; Wooland, J. R. & Macherey, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Report on Low Columbium: Uranium Corrosion Resistant Alloys

Description: Uranium alloys containing 3 and 6 w/o niobium have been prepared in which the impurity content is rather low. These alloys show very promising resistance to corrosion by water at 260 and 300 degree C. The corrosion resistance is exhibited in degassed water and in water which is saturated with air or oxygen at room temperature before testing.
Date: June 24, 1953
Creator: Draley, Joseph Edward, 1919-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Improved Continuous Ether Extractor for the Determination of Uranium in Dissolver Solutions

Description: An improved continuous ether extractor is described. The modifications include a means of safely disposing of the active raffinate and a means of positivity checking the raffinate for completeness of uranium extraction. The results obtained on synthetic samples and on dissolver solutions are given. This work was undertaken because of a need for the determination of uranium in dissolver solutions with an accuracy of 0.1 per cent. After a review of available methods it was decided that a gravimet… more
Date: August 27, 1953
Creator: Bane, R. W. & Jensen, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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