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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 crit… more
Date: May 25, 1959
Creator: Aerojet-General Corporation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho

Description: Report that "summarizes the costs, experience and results of contracts AT(10-1)-1054 and AT(10-1)-1122 for drilling, casing and cementing observation wells at the National Reactor Testing Station, Idaho" (p. [11]).
Date: May 1, 1963
Creator: Keys, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrology of Subsurface Waste Disposal, National Reactor Testing Station, Idaho : Annual Progress Report, 1963

Description: From introduction: "The present report indicates additional preliminary progress in the interpretation of the geology of the area on the basis of preliminary gravity and magnetic surveys and sketches the progress made in operational phases of the study of the hydrology of waste disposal."
Date: May 1964
Creator: Morris, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials Testing Reactor-Engineering Test Reactor Technical Branches Quarterly Report: October 1 - December 31, 1963

Description: From summary: "Reactor fuel material consisting of U3Si particles embedded in an aluminum matrix have been examined with an electron microprobe to determine reaction between fuel particles and matrix. Partial reaction was observed with no observable tendency for the uranium or silicon to diffuse outward into the matrix.
Date: May 1964
Creator: Phillips Petroleum Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EOCR Control Rod and Driver Fuel Hydraulic Tests

Description: Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

Description: From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date: July 12, 1963
Creator: Zelezny, W. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Description: Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

Description: The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date: June 1965
Creator: Fletcher, R. D.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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