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Engineering Properties of Diphenyl

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.
Date: August 11, 1953
Creator: Anderson, Kermit
Item Type: Report
Partner: UNT Libraries Government Documents Department

The Expulsion of Liquid from a Rapidly Heated Channel

Description: 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.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

Description: 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.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: October-December 1975

Description: This effort is being directed toward support studies for the national endeavor on in situ coal gasification. This task involves the investigation of reaction-controlling variables and product distributions for the gasification of both coals and chars utilizing steam and oxygen. Included in this task is the investigation of the effects of using brackish water as the water supply. The high-pressure char gasification system has been received from the manufacturer and is currently undergoing testing. The types of experiments that would be most useful in their studies have been discussed with two of the three laboratories carrying out field tests of in-situ gasification.
Date: 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Description: 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.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Heat Generation in Irradiated Uranium

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.
Date: February 25, 1952
Creator: Untermyer, Samuel & Weills, J. T.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia

Description: From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."
Date: June 1963
Creator: Weatherhead, R. J.
Item Type: Report
Partner: UNT Libraries Government Documents Department

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

Description: 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.; Dickerman, Charles E. & Stephany, William P.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Idaho Division Summary Report

Description: 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: Novick, Meyer & Thalgott, F. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Idaho Division Summary Report: July, August, September, 1960

Description: 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: Novick, Meyer & Thalgott, F. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

Description: 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.
Item Type: Report
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Item Type: Report
Partner: UNT Libraries Government Documents Department

Liquid MHD Power Cycle Studies

Description: 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
Item Type: Report
Partner: UNT Libraries Government Documents Department

LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970

Description: Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs.
Date: July 1971
Creator: Simmons, W. R. & Marchaterre, J. F.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility

Description: 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
Item Type: Report
Partner: UNT Libraries Government Documents Department

A Multiple-Source Urban Atmospheric Dispersion Model

Description: Report documenting the development phase of a multiple-source, urban atmospheric dispersion model that describes environmental transients.
Date: May 1970
Creator: Roberts, John J.; Croke, E. J.; Kennedy, A. S.; Norco, J. E. & Conley, L. A.
Item Type: Report
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

Description: From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the temperature field to be found in Section II below."
Date: December 1966
Creator: Valentin, Richard A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Optimization of Efficiency of a Cesium Diode Converter

Description: From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."
Date: March 1962
Creator: Sanathanan, C. K.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Crewe, Albert V.; FitzPatrick, John P. & Manson, David S.
Item Type: Report
Partner: UNT Libraries Government Documents Department