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Breeding-Gain Specimens for EBR-I Core IV

Description: Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1963
Creator: Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.

A Lunar Power Plant

Description: Report issued by the Argonne National Laboratory over studies conducted on designs for a lunar power plant. As stated in the abstract, "a concept of a nuclear power plant to be assembled on earth and operated on the moon in presented" (p. 9). This report includes tables, illustrations, and photographs.
Date: December 1960
Creator: Armstrong, R. H.; Carter, J. C.; Hummel, H. H.; Janicke, M. J. & Marchaterre, J. F.

Transistor Scintillation Spectrometer

Description: Report describing "an AC-operated portable scintillation spectrometer consisting of a preamplifier, a linear pulse amplifier, a single-channel pulse-height analyzer, a linear count-rate meter, a scaler, and a high-voltage power supply. The operation and performance of the circuits are discussed" (p. 3).
Date: February 1960
Creator: Strauss, Michael G.

Argonaut Automatic Flux Controller Design Report

Description: Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.
Date: January 1960
Creator: Gerba, A., Jr.

A Low Dead-Time Neutron-Counting-System

Description: From Abstract: "This report describes a counting system capable of processing input pulses at an average rate in excess of 3 x 10 to the fifth power counts per second with less than 10 percent counting loss due to instrumental dead time."
Date: January 1961
Creator: Epstein, Robert J. & Thompson, Donald C.

A Performance Analysis of the EBWR at Various Power Levels

Description: From Introduction: "This study is an attempt to predict the operating performance of EBWR (Experimental Boiling Water Reactor) at various power levels. It was done at the same time that EWBR was raised in power up to 100 MW, and so an excellent possibility was given to check the validity of the used performance analysis. Rather than giving a general and complete outline of the analysis or establishing a new approach, the study outlines and specifies the numerous practical problems involved in this analysis, and tries to explain the discrepancies between predicted and experimental results."
Date: October 1963
Creator: Nentwich, Alfred A.

Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

Description: From Abstract: "Discussed in the paper are the production of the uranium fuel alloy, the fabrication of the cladding components from Zircaloy-2 ingot, the assembly, welding, evacuation, and sealing of the cladding billets, the jacketing of the cladding billets with steel, and the roll bonding, heat treatment, stripping, and cleaning of the fuel plates. Evaluation of the fuel plates produced is also included."
Date: June 1957
Creator: Macherey, R. E.; Bean, C. H.; Carson, N. J., Jr. & Lindgren, J. R.

Preliminary Design of a Basic Radiation Effects Reactor (BRER)

Description: From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. the peak of the neutron-energy spectrum should be variable within the approximate range from 10 to 1000 kev."
Date: March 1961
Creator: MacFarlane, D. R.; Rohde, R. R.; Toppel, B.; Charak, I. & Unger, H.

Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Description: From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."
Date: February 1960
Creator: Argonne National Laboratory

Resistance of Materials to Attack by Liquid Metals

Description: From Forward: "As their contribution, the Metallurgy Division of Argonne National Laboratory was asked to assemble all available unclassified and declassifiable data on the resistance of materials to attack by liquid metals. The resulting collation of data is contained in this report."
Date: July 1950
Creator: Kelman, LeRoy R.; Wilkinson, Walter D. & Yaggee, Frank L.

A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II

Description: From Abstract: "A detailed description is given of ARGUS, a FORTRAN II computer program for calculating transient temperatures in any concentric cylindrical configuration. Included are an explanation of the mathematical methods, a discussion of special features and restrictions, input and output descriptions, operating instructions, several sample problems, and the code listing."
Date: November 1963
Creator: Schoeberle, D. F.; Heestand, J.; Miller, L. B. & Miller, L. B.