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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: AEC research and development report
 Serial/Series Title: ANL (Series)
 Collection: Technical Report Archive and Image Library
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
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
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
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.; 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
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
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
Liquid MHD Power Cycle Studies

Liquid MHD Power Cycle Studies

Date: June 1965
Creator: Petrick, Michael & Lee, Kung-You
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.
Contributing Partner: UNT Libraries Government Documents Department
Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

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

Date: February 1959
Creator: Crewe, Albert V.; FitzPatrick, John P. & Manson, David S.
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.
Contributing Partner: UNT Libraries Government Documents Department
Particle Accelerator Division Summary Report: April Through September 1960

Particle Accelerator Division Summary Report: April Through September 1960

Date: 1960
Creator: Crewe, Albert V.; FitzPatrick, John P.; Foss, Martyn H. & Manson, David S.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Performance Characteristics of a Liquid Metal MHD Generator

Performance Characteristics of a Liquid Metal MHD Generator

Date: July 1964
Creator: Petrick, Michael & Lee, Kung-You
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Quarterly Progress Report on Reactor Development: 4000 program

Quarterly Progress Report on Reactor Development: 4000 program

Date: July 31, 1954
Creator: McLain, Stuart
Description: Report issued by the Argonne National Laboratory discussing progress made on reactor development. Progress made on the core, pressure vessel and shield, and the power plant are presented. This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Development Program Progress Report: April 1963

Reactor Development Program Progress Report: April 1963

Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Development Program Progress Report: March 1963

Reactor Development Program Progress Report: March 1963

Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Development Program Progress Report: May 1966

Reactor Development Program Progress Report: May 1966

Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Development Program Progress Report: November 1965

Reactor Development Program Progress Report: November 1965

Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Development Program Progress Report: September 1966

Reactor Development Program Progress Report: September 1966

Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Date: March 1961
Creator: Yaggee, F. L.
Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Selected Values of the Physical Properties of Various Materials

Selected Values of the Physical Properties of Various Materials

Date: September 1958
Creator: Tebo, F. J.
Description: Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department