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  Partner: UNT Libraries Government Documents Department
 Decade: 1960-1969
 Collection: Technical Report Archive and Image Library
Proceedings of the AMU-ANL Summer Study Program

Proceedings of the AMU-ANL Summer Study Program

Date: November 1962
Creator: Pearson, C. V.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Status Report on the Argonne Advanced Research Reactor

Status Report on the Argonne Advanced Research Reactor

Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Description: None
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
Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Date: March 1961
Creator: MacFarlane, D. R.; Rohde, R. R.; Toppel, B.; Charak, I. & Unger, H.
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
Recrystallization in Rolled Uranium Sheet

Recrystallization in Rolled Uranium Sheet

Date: March 1962
Creator: Lloyd, Lowell T. & Mueller, Melvin H.
Description: None
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
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques

A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques

Date: November 1961
Creator: Levitz, N.; Barghusen, J.; Carls, E. & Jonke, A. A.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics

Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics

Date: February 1962
Creator: Lottes, P. A.
Description: Report discussing state of the art design and operation of heat transfer and hydraulics equipment and technology in boiling water reactor power plants.
Contributing Partner: UNT Libraries Government Documents Department
Operational Tests of EBWR Vapor Recovery System

Operational Tests of EBWR Vapor Recovery System

Date: August 1960
Creator: Gariboldi, R. J. & Jacobson, D. R.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter

A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter

Date: March 1961
Creator: Yaggee, F. L.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
The Electrical Design of the EBR-II

The Electrical Design of the EBR-II

Date: June 1966
Creator: Verber, F. & Schmidt, H. L.
Description: Report that "summarizes the electrical design of the Experimental Breeder Reactor II Facility (EBR-II). It attempts to gather together and present in reasonable detail the essential features and workings of the completed design, and to present a concise overall view of the system" (p. 11).
Contributing Partner: UNT Libraries Government Documents Department
XLIBIT: ANL Cross-section Library Code

XLIBIT: ANL Cross-section Library Code

Date: February 1966
Creator: Sparck, S. D.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

Date: December 1966
Creator: Valentin, Richard A.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
The Mass Transfer of Single, Solid Uranium Spheres to Flowing Molten Cadmium in Laminar and Turbulent Flow

The Mass Transfer of Single, Solid Uranium Spheres to Flowing Molten Cadmium in Laminar and Turbulent Flow

Date: September 1965
Creator: Traylor, E. Dean
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A Liquid-Metal Heat-Transfer Experiment

A Liquid-Metal Heat-Transfer Experiment

Date: June 1965
Creator: Holtz, R. E.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions

A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions

Date: April 1966
Creator: Schmidt, Klaus H.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Bending of Circular Plates Under A Variable Symmetrical Load

Bending of Circular Plates Under A Variable Symmetrical Load

Date: April 1964
Creator: Heap, J. C.
Description: Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron.
Contributing Partner: UNT Libraries Government Documents Department
Frequency-Response Analysis of Steam Voids to Sinusoidal Power Modulation in a Thin-Walled Boiling Water Coolant Channel

Frequency-Response Analysis of Steam Voids to Sinusoidal Power Modulation in a Thin-Walled Boiling Water Coolant Channel

Date: May 1965
Creator: St. Pierre, Carl C.
Description: Report regarding a study with the primary objective of acquiring "experimental data on power-to-void transfer functions for a single rectangular flow channel at elevated pressures" (p. 9).
Contributing Partner: UNT Libraries Government Documents Department
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface

Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface

Date: March 1964
Creator: Kudirka, A. A.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Propagation of Density Disturbances in Air-Water Flow

Propagation of Density Disturbances in Air-Water Flow

Date: June 1965
Creator: Nassos, George P.
Description: None
Contributing Partner: UNT Libraries Government Documents Department