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Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
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.
System:
The UNT Digital Library
Particle Accelerator Division Summary Report: April Through September 1960
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.
System:
The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
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.
System:
The UNT Digital Library
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate
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.
System:
The UNT Digital Library
Gas-Cooled Reactors in the USA: A Survey and Recommendation
Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Date:
November 1960
Creator:
Armstrong, R. H.
System:
The UNT Digital Library
Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961
Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
Date:
1961
Creator:
Argonne National Laboratory. Idaho Division.
System:
The UNT Digital Library
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date:
March 1961
Creator:
Yaggee, F. L.
System:
The UNT Digital Library
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters
Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Date:
October 1961
Creator:
Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
System:
The UNT Digital Library
Facility For Photographing in-Pile Meltdown Experiments in TREAT
Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date:
January 1962
Creator:
Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
System:
The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design
Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date:
September 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
System:
The UNT Digital Library
The Facility 350 Helium-Atmosphere System
Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.
Date:
December 1962
Creator:
Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
System:
The UNT Digital Library
Reactor Development Program Progress Report: March 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
April 15, 1963
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
Reactor Development Program Progress Report: April 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
May 15, 1963
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date:
July 1963
Creator:
Vogrin, Joseph A., Jr.
System:
The UNT Digital Library
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat
Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Date:
December 1963
Creator:
Kramer, W. C. & Bean, C. H.
System:
The UNT Digital Library
Argonne National Laboratory Metallurgy Division Annual Report: 1963
Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
Date:
1964
Creator:
Foote, Frank G.; Chiswik, Haim H. & Macherey, Robert E.
System:
The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
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.
System:
The UNT Digital Library
Performance Characteristics of a Liquid Metal MHD Generator
Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
Date:
July 1964
Creator:
Petrick, Michael & Lee, Kung-You
System:
The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers
Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date:
September 1964
Creator:
Stein, Ralph P.
System:
The UNT Digital Library
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Date:
October 1964
Creator:
Wilhelm, Donald J.
System:
The UNT Digital Library
A Study of Convective Magnetohydrodynamic Channel Flow
Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date:
March 1965
Creator:
Singer, Ralph M.
System:
The UNT Digital Library
Liquid MHD Power Cycle Studies
Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.
Date:
June 1965
Creator:
Petrick, Michael & Lee, Kung-You
System:
The UNT Digital Library
Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop
Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date:
August 1965
Creator:
Jain, Kamal C.
System:
The UNT Digital Library
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date:
September 1965
Creator:
Baker, James L. L.
System:
The UNT Digital Library