You limited your search to:

  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: ANL (Series)
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Argonne National Laboratory Annual Report: 1956

Argonne National Laboratory Annual Report: 1956

Date: 1956
Creator: Argonne National Laboratory
Description: Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1956. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Argonne National Laboratory Annual Report: 1957

Argonne National Laboratory Annual Report: 1957

Date: 1957
Creator: Argonne National Laboratory
Description: Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1957. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Argonne National Laboratory Annual Report: 1958

Argonne National Laboratory Annual Report: 1958

Date: 1958
Creator: Argonne National Laboratory
Description: Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1958. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Calculations on U235 Fission Product Decay Chains

Calculations on U235 Fission Product Decay Chains

Date: May 1952
Creator: Faller, I. L.; Chapman, T. S. & West, J. M.
Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation

Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation

Date: October 1964
Creator: Wilhelm, Donald J.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Design and Testing of a High-Heat Flux Electron-Bombardment Heater

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

Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
The EBWR: Experimental Boiling Water Reactor

The EBWR: Experimental Boiling Water Reactor

Date: May 1957
Creator: Argonne National Laboratory
Description: Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Electronic Distribution Functions and Thermodynamic Properties at High Temperatures

Electronic Distribution Functions and Thermodynamic Properties at High Temperatures

Date: May 1953
Creator: Brachman, Malcolm K. & Meyerott, Roland E.
Description: Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Engineering, Construction and Cost of the Argonaut Reactor

Engineering, Construction and Cost of the Argonaut Reactor

Date: March 1957
Creator: Armstrong, R. H.; Kolb, W. L.; Lennox, D. H.; Kelber, C. N.; Selep, Andrew & Spinrad, B. I.
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
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

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

Date: September 1965
Creator: Baker, James L. L.
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.
Contributing Partner: UNT Libraries Government Documents Department
Gasification of Chars Produced Under Simulated in situ Processing Conditions Quarterly Report: October-December 1975

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

Date: 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A.
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.
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.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
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 & Weills, J. T.
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.; Dickerman, Charles E. & Stephany, William P.
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. & Crothers, C. C.
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
IsotopesProduction Reactor: Summary of Complete Design

IsotopesProduction Reactor: Summary of Complete Design

Date: 1955
Creator: Winkleblack, R. K
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Lecture Notes on Reactor Shielding

Lecture Notes on Reactor Shielding

Date: March 1959
Creator: Grotenhuis, Marshall
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.
Contributing Partner: UNT Libraries Government Documents Department
FIRST PREV 1 2 3 NEXT LAST