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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: ANL (Series)
 Collection: Technical Report Archive and Image Library
Engineering, Construction and Cost of the Argonaut Reactor

Engineering, Construction and Cost of the Argonaut Reactor

Date: March 1957
Creator: Armstrong, R. H.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Engineering development of fluid-bed fluoride volatility processes

Engineering development of fluid-bed fluoride volatility processes

Date: 1964
Creator: Vogel, G. J.
Description: None
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
The Expulsion of Liquid from a Rapidly Heated Channel

The Expulsion of Liquid from a Rapidly Heated Channel

Date: May 1967
Creator: Singer, Ralph M.
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.
Contributing Partner: UNT Libraries Government Documents Department
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction

Date: April 1966
Creator: Koppel, L. B.
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.
Contributing Partner: UNT Libraries Government Documents Department
Heat Generation in Irradiated Uranium

Heat Generation in Irradiated Uranium

Date: February 25, 1952
Creator: Untermyer, Samuel
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
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

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

Date: September 1967
Creator: Bryant, Lawrence T.
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.
Contributing Partner: UNT Libraries Government Documents Department
Idaho Division Summary Report

Idaho Division Summary Report

Date: 1961
Creator: Novick, Meyer & Thalgott, F. W.
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.
Contributing Partner: UNT Libraries Government Documents Department
Idaho Division Summary Report: July, August, September, 1960

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

Date: 1960
Creator: Novick, Meyer & Thalgott, F. W.
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.
Contributing Partner: UNT Libraries Government Documents Department
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

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

Date: July 1960
Creator: Gavin, A. P.
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.
Contributing Partner: UNT Libraries Government Documents Department