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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev

Description: Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date: May 29, 1958
Creator: Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Temperatures in Infinite Plates, Infinite Cylinders, and Spheres During Convective Cooling from Initially Parabolic Temperature Profiles

Description: Report presenting "the evaluations of the series which represent the solutions to the Fourier equation in rectangular, cylindrical and spherical coordinates for the case in which the initial temperature field is that owing to a spatially uniform heat source" (p. 1).
Date: 1958
Creator: Epel, Lester G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Standard Practices Guide for Writing Experimental Operating Manuals

Description: This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
Date: December 15, 1958
Creator: Ford, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Potential Applications of Nuclear Energy for Process and Space Heat in the United States

Description: A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date: October 1958
Creator: Geiringer, Paul Ludwig & Goodfriend, Morton J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Organic Reactor Waste Gas Analyzer

Description: The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date: October 15, 1958
Creator: Gilroy, H. M. & Edwards, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary Report on Thorium Metal Quality for Production Reactor Use

Description: From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as th… more
Date: July 1958
Creator: Hayes, Edgar E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement to Standard Practices for Design of MTR and ETR Safety Circuits

Description: Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
Date: November 21, 1958
Creator: Jones, L. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Problems of Obtaining Thermonuclear Temperatures

Description: This report discusses the problem of obtaining thermonuclear temperatures as part of reaching a controlled fusion reaction for fusion power. Tables covering radiation losses and thermonuclear reaction rates are included. Talk before JCAEC in Washington, D. C.
Date: January 29, 1958
Creator: Post, Richard F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fluidization in Tapered Beds

Description: Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.
Date: February 14, 1958
Creator: Rossmassler, W. R. & Harris, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Selected Values of the Physical Properties of Various Materials

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.
Date: September 1958
Creator: Tebo, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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