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
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
The Expulsion of Liquid from a Rapidly Heated Channel (open access)

The Expulsion of Liquid from a Rapidly Heated Channel

Report documenting experiments in order to determine the "behavior of a partially confined liquid in contact with a rapidly heated surface" (p. 7). These liquids include water, methanol, ethylene bromide, and acetone.
Date: May 1967
Creator: Singer, Ralph M.
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
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
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
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
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
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
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
A Study of Convective Magnetohydrodynamic Channel Flow (open access)

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
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation (open access)

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
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers (open access)

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
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
Argonne National Laboratory Metallurgy Division Annual Report: 1963 (open access)

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 (open access)

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
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat (open access)

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

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
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
The Facility 350 Helium-Atmosphere System (open access)

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

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
Facility For Photographing in-Pile Meltdown Experiments in TREAT (open access)

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
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters (open access)

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