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Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

Description: Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
Date: July 1960
Creator: Gavin, A. P. & Crothers, C. C.
Partner: UNT Libraries Government Documents Department
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Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

Description: From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
Date: May 1960
Creator: Gavin, A. P.
Partner: UNT Libraries Government Documents Department
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Argonne National Laboratory Idaho Division Summary Report: July-September, 1960

Description: Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Argonne National Laboratory. Idaho Division.
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April Through September 1960

Description: Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Crewe, Albert V.; FitzPatrick, John P.; Foss, Martyn H. & Manson, David S.
Partner: UNT Libraries Government Documents Department
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Operating Manual for the Argonaut Reactor

Description: The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities… more
Date: August 1959
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
Partner: UNT Libraries Government Documents Department
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Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Argonne National Laboratory. Particle Accelerator Division.
Partner: UNT Libraries Government Documents Department
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The Fabrication of a Plutonium Helix for a Doppler Experiment

Description: A helix constructed of plutonium was made to test the Doppler temperature effect in ZPR-III. The helix, 1 inch in diameter and 6-1/4 inches long, contained 240 grams of delta-phase plutonium alloy encapsulated in titanium tubing. Four plutonium rods were extruded, joined together, and pushed into a titanium tube. This tube was swaged tightly over the plutonium rod, and the assembly was wound into a coil. Electrical leads to the coil were made by swaging copper tubing over the ends of the coil. … more
Date: December 1958
Creator: Dunworth, R. J.; Rhude, H. V. & Kelman, L. R.
Partner: UNT Libraries Government Documents Department
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Selected Values of the Physical Properties of Various Materials

Description: Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.
Date: September 1958
Creator: Tebo, F. J.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report for January, February, and March 1958

Description: Development work was continued on the fused fluoride process for the recovery of enriched uranium from zirconium-matrix fuel alloys. The alloy is dissolved by immersing it in molten sodium fluoride-zirconium fluoride at 600°C and passing hydrogen fluoride vapor through the system.The dissolved uranium tetrafluoride in the melt is then volatilized as uranium hexafluoride by sparging with fluorine. The uranium hexafluoride product is purified and decontaminated by fractional distillation. Additio… more
Date: June 1958
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Two-Phase Air-Water Flow Phenomena

Description: Report issued by the Argonne National Laboratory discussing two-phase flow studies that were conducted "to obtain empirical density relationships and pressure drop friction factors for two-phase mixtures" (p. 11). This report includes tables, illustrations, and photographs.
Date: March 1958
Creator: Petrick, Michael
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1957

Description: Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hy… more
Date: December 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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A laboratory Ivestigation of the Fluorination of Crude Uranium Tertrafluoride

Description: Ore concentrates have been converted directly to crude uranium tetrafluoride by hydrogen reduction and hydrofluorination in fluidized-bed reactors. Small-scale laboratory experiments demonstrated that this process can be extended to the production of crude uranium hexafluoride through fluorination of the uranium tetrafluoride in a fluidized bed. The satisfactory temperature range for the reaction lies between 300°C and 600°C. At 450°C the fluorine utilization is between 50 and 80 per cent. With… more
Date: December 1957
Creator: Sandus, O. & Steunenberg, R. K.
Partner: UNT Libraries Government Documents Department
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A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C

Description: The feasibility of the coated metal crucible as a container for eutectic Al-Si alloy has been proven by test. Small, enamel-coated cast iron pots has been proven by test. Small, enamel-coated cast iron pots have successfully withstood the chemically aggressive Al-Si alloy and the adverse influence of an oxidizing atmosphere for a period of 3 months at 725°C. A similarly coated castiron crucible containing 450 pounds of eutectic Al-Si alloy was successfully tested for 144 days in a jacketing ope… more
Date: November 1957
Creator: Yaggee, F. L.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report for January, February, and March 1957

Description: A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.
Date: July 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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The EBWR: Experimental Boiling Water Reactor

Description: Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.
Date: May 1957
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1956

Description: A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
Date: March 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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Quarterly Report October, November and December, 1956

Description: Methods of producing extremely clean surfaces on rolled Zircaloy-2 strip have been investigated. It has been found that the finer abrasives, 400 mesh or finer, are more effective than coarse types because of their ability to penetrate pits and crevices more readily. Two such cleanings, with an intermediate 35 v/o HNO3-5 v/o HF pickle, resulted in a microscopically clean surface. Ultrasonic inspection of the EBWR fuel plates has been completed during this quarter. Approximately 95% of the plates… more
Date: December 31, 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report July, August, and September, 1956

Description: Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol … more
Date: December 1956
Creator: Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Partner: UNT Libraries Government Documents Department
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