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MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650

Description: Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date: 1962
Creator: Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
Partner: UNT Libraries Government Documents Department
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Summary of the Spert-I, -II, and -III reactor facilities

Description: Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date: November 1, 1957
Creator: Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
Partner: UNT Libraries Government Documents Department
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Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I

Description: Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date: January 24, 1958
Creator: deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
open access

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date: April 1, 1958
Creator: Kaiser Engineers
Partner: UNT Libraries Government Documents Department
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Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
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Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels

Description: Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date: June 20, 1962
Creator: Chamberlain, H. V.
Partner: UNT Libraries Government Documents Department
open access

ICPP Waste Calcining Facility : Safety Analysis Report

Description: Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
Date: December 1, 1963
Creator: Lakey, L. T. & Bower, J. R.
Partner: UNT Libraries Government Documents Department
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