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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
 Collection: Technical Report Archive and Image Library
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Date: July 1961
Creator: Misch, R. D. & Van Drunen, C.
Description: Report concerning the corrosion of several ternary zirconium alloys using distilled water at 350 degrees Celsius or ssteam heated to 540 degrees Celsius and 600 psi.
Contributing Partner: UNT Libraries Government Documents Department
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

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

Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
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.
Contributing Partner: UNT Libraries Government Documents Department
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Contributing Partner: UNT Libraries Government Documents Department
Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Date: May 1961
Creator: Argonne National Laboratory
Description: Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards.
Contributing Partner: UNT Libraries Government Documents Department
Design and Performance Characteristics of Magnetic Jack-Type Control Rod Drive

Design and Performance Characteristics of Magnetic Jack-Type Control Rod Drive

Date: December 1957
Creator: Young, Joseph N.
Description: Report concerning the design of the magnetic jack, which is a "hermetically sealed, step-motion linear motor which satisfies the need for a reliable, low-cost, nuclear reactor control rod drive." (p. 5)
Contributing Partner: UNT Libraries Government Documents Department
Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
Description: Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Design of the Argonne Low Power Reactor (ALPR)

Design of the Argonne Low Power Reactor (ALPR)

Date: May 1961
Creator: Hamer, E. E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15)
Contributing Partner: UNT Libraries Government Documents Department
Design Summary Report on the Juggernaut Reactor

Design Summary Report on the Juggernaut Reactor

Date: September 1962
Creator: Folkrod, J. R.; Ember, G.; Kolb, W.; Saluja, J. & Moon, D. P.
Description: Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

Date: June 1963
Creator: Nassos, George P.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Development of Techniques for Fabrication of Small-Diameter Thin-Wall Tungsten Tubing: Interim Progress Report covering the period from July 1, 1963 through December 31, 1963

Development of Techniques for Fabrication of Small-Diameter Thin-Wall Tungsten Tubing: Interim Progress Report covering the period from July 1, 1963 through December 31, 1963

Date: 1964
Creator: Burt, W. R., Jr.; Katiyar, H. C. & Mayfield, R. M.
Description: Report describing the methods and equipment used to extrude tungsten tubing from various starting materials.
Contributing Partner: UNT Libraries Government Documents Department