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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
 Collection: Technical Report Archive and Image Library
The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems

The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems

Date: March 1956
Creator: Alstad, C. D.; Isbin, H. S.; Amundson, N. R. & Silvers, J. P.
Description: Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
A Physical Determination of the Conversion Ratio of the Experimental Breeder Reactor

A Physical Determination of the Conversion Ratio of the Experimental Breeder Reactor

Date: August 1954
Creator: Curtis, C. D.; Klein, S. H.; Okrent, D.; Redman, W. C. & Untermyer, Samuel
Description: Report issued by the Argonne National Laboratory discussing the Experimental Breeder Reactor (EBR). Descriptions and methods of the EBR are presented. This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Heat Generation in Irradiated Uranium

Heat Generation in Irradiated Uranium

Date: February 25, 1952
Creator: Untermyer, Samuel & Weills, J. T.
Description: Report issued by the Argonne National Laboratory discussing the heat generation of irradiated uranium. Methods of heat production in uranium are presented. This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Engineering Properties of Diphenyl

Engineering Properties of Diphenyl

Date: August 11, 1953
Creator: Anderson, Kermit
Description: Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952

Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952

Date: March 1952
Creator: Brues, A. M. & Buchanan, D. L.
Description: Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
Contributing Partner: UNT Libraries Government Documents Department
Progress Report on the Argonne-Oak Ridge Digital Computer

Progress Report on the Argonne-Oak Ridge Digital Computer

Date: March 5, 1951
Creator: Birge, W. A.; Burdette, E. W.; Burks, A. W.; Chu, J. C.; Flanders, D. A.; Jacobsohn, D. H. et al.
Description: Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.
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Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)

Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)

Date: 1958
Creator: West, J. M.; Dietrich, J. R.; Jameson, A. S.; Anderson, G. A.; Harrer, J. M. & Brush, H. F.
Description: Report discussing possible hazards and preliminary safeguards for a 20-megawatt Experimental Boiling Water Reactor (EBWR) power plant
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
Experimental Breeder Reactor-II (EBR-II) Shield Design

Experimental Breeder Reactor-II (EBR-II) Shield Design

Date: September 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

Date: April 1964
Creator: Sanathanan, Chathilingath K.
Description: Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5)
Contributing Partner: UNT Libraries Government Documents Department
The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field

The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field

Date: July 1964
Creator: Singer, Ralph M.
Description: Report issued by the Argonne National Laboratory over "the use of an electromagnetic field to control the laminar film condensation of a vapor whose liquid is electrically conducting" (p. 7). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

Date: July 1963
Creator: Vogrin, Joseph A., Jr.
Description: 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).
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
The Facility 350 Helium-Atmosphere System

The Facility 350 Helium-Atmosphere System

Date: December 1962
Creator: Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
Description: 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.
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
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Description: 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.
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
U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

Date: December 1960
Creator: Fromm, Leonard W., Jr.
Description: None
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
Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Date: October 1961
Creator: Long, J. K.; McVean, R. L.; Thalgott, F. W. & Novick, M.
Description: Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents.
Contributing Partner: UNT Libraries Government Documents Department
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
EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Description: Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.)
Contributing Partner: UNT Libraries Government Documents Department
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department