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Reactor Development Program Progress Report: April 1963 (open access)

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
Reactor Development Program Progress Report: March 1963 (open access)

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: May 1966 (open access)

Reactor Development Program Progress Report: May 1966

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: November 1965 (open access)

Reactor Development Program Progress Report: November 1965

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Reactor Development Program Progress Report: September 1966 (open access)

Reactor Development Program Progress Report: September 1966

Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
System: The UNT Digital Library
Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility (open access)

Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility

Report issued by the Argonne National Laboratory discussing the proposal of the Midwest Tandem-Cyclotron accelerator facility. Descriptions of the facility designs, methods, and operations are presented. This report includes tables, illustrations, and photographs.
Date: June 1969
Creator: Argonne National Laboratory
System: The UNT Digital Library
Annual Report 1961 (open access)

Annual Report 1961

This seventh Annual Report is a summary of some of the progress in scientific and engineering research and development carried on at Argonne National Laboratory during 1961. As is customary in this series, only those portions of the total program that have reached such a stage that they may be of general interest are recorded. Thus, a comparison with the Annual Reports for 1959 (ANL-6125) and for 1960 (ANL-6275) will reveal the description of a generally different set of scientific activities. A more detailed presentation of any work covered in this report or of the many ANL projects not mentioned may be obtained by perusing the various progress and topical reports issued by the Laboratory during 1961. A list of the publications in the scientific journals during 1961 by Argonne personnel has been given as an Appendix.
Date: 1961
Creator: Argonne National Laboratory (ANL)
System: The UNT Digital Library
Argonne National Laboratory Idaho Division Summary Report: July-September, 1960 (open access)

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
Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961 (open access)

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
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow (open access)

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
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments (open access)

A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations.
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
System: The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant (open access)

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
Design and Testing of a High-Heat Flux Electron-Bombardment Heater (open access)

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

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.
Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
System: The UNT Digital Library
Particle Accelerator Division Summary Report: April Through September 1960 (open access)

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
Metallurgy Division Quarterly Report [for] October, November, and December 1955 (open access)

Metallurgy Division Quarterly Report [for] October, November, and December 1955

A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the elimination of frequently observed segmented inclusions at the seal pin interfaces.
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
System: The UNT Digital Library
Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate (open access)

Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

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.
System: The UNT Digital Library
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate (open access)

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
Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point (open access)

Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point

From Introduction: "Interest in utilizing natural-circulation loops to obtain results that aid in the design of some boiler and nuclear reactor coolant systems has focused attention on the dynamic behavior of such loops. Much analytical and experimental work has been done so as to permit predictions of the transient behavior of both single-phase and two-phase neutral-circulation systems. The analytical portion of the study consisted of simulating the loop by utilizing a digital computer to predict the measured transients."
Date: May 1963
Creator: Harden, Darrel G.
System: The UNT Digital Library
Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop (open access)

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
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction (open access)

A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date: April 1966
Creator: Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
System: The UNT Digital Library
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface (open access)

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

From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."
Date: March 1964
Creator: Kudirka, A. A.
System: The UNT Digital Library
Proceedings of the AMU-ANL Summer Study Program (open access)

Proceedings of the AMU-ANL Summer Study Program

From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Date: November 1962
Creator: Pearson, C. V.
System: The UNT Digital Library
Liquid MHD Power Cycle Studies (open access)

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
Performance Characteristics of a Liquid Metal MHD Generator (open access)

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