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PRTR second generation shim assembly

Description: From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
Partner: UNT Libraries Government Documents Department
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Production of Zirconium at Y-12

Description: Abstract: "A general description is given of the permanent zirconium plant at Y-12. Equipment is described and materials of construction are listed. Photographs illustrating principal equipment and reduced construction drawings are also presented. Operating conditions and costs information are listed."
Date: November 17, 1955
Creator: Ramsey, J. W. & Whitson, W. K., Jr.
Partner: UNT Libraries Government Documents Department
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Status Report and Plant Proposals for Zirconium Purification

Description: From abstract: "This report contains a summary of the latest improvements in zirconium purification as developed by the Y-12 research, pilot plant, production, and engineering groups, all of whom have been generously cooperating in this project."
Date: November 18, 1955
Creator: Leaders, W. M.
Partner: UNT Libraries Government Documents Department
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Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Description: Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as … more
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Partner: UNT Libraries Government Documents Department
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Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Description: Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove … more
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Partner: UNT Libraries Government Documents Department
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SM-2 Critical Experiments : CE-1

Description: Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, … more
Date: November 30, 1959
Creator: Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle Program Annual Report, Fiscal Year 1958

Description: Report that describes work performed by by the Hanford Laboratories Operation on the Plutonium Recycle Program during the Fiscal Year.
Date: November 11, 1958
Creator: Hanford Atomic Products Operation
Partner: UNT Libraries Government Documents Department
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NS Savannah Upgrading Analog Computer Analysis

Description: From abstract: "This work amplified previous design studies by considering accidents of greater severity, automatic limiting devices to preclude safety action, and more realistic parameters based on operating experience."
Date: November 1962
Creator: Rosser, R. M.
Partner: UNT Libraries Government Documents Department
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Final Engineering Report Covering Austin Beta-Gamma Hand and Foot Checker

Description: Abstract: "This final report discusses the project objectives and the manner in which these were attained in connection with the design and manufacture of the Austin Beta-Gamma Hand and Foot checker (Fig 1). Improvements incorporated to conform the equipment to modern production methods, as well as practical changes to achieve automatic operation and increased stability and to facilitate and simplify maintenance procedures, are covered in detail. The report also includes photographs (Figs. 2 … more
Date: November 9, 1949
Partner: UNT Libraries Government Documents Department
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Steam-Cooled Power Reactor Evaluation: Mixed Spectrum Superheater

Description: From introduction: "This report provides the preliminary design for the nuclear portion of a 300 MWe Mixed Spectrum Superheater to be in operation by 1967.
Date: November 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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The Post-Irradiation Examination of a PuOâ‚‚-UOâ‚‚ Fast Reactor Fuel

Description: From abstract: "Post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement central voids, and metallographic examination of selected samples.
Date: November 1961
Creator: Gerhart, J. M.
Partner: UNT Libraries Government Documents Department
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Comparative Study of PuC-UC and PuOâ‚‚-UOâ‚‚ as Fast Reactor Fuel

Description: From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date: November 15, 1962
Creator: Collins, G. D.
Partner: UNT Libraries Government Documents Department
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Experimental Studies of Transient Effects in Fast Reactor Fuels

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F.… more
Date: November 15, 1962
Creator: Field, J. H.
Partner: UNT Libraries Government Documents Department
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Sodium Components Test Facility

Description: Development of more reliable, lower cost components for high temperature liquid metal-cooled reactor plants.
Date: November 1959
Partner: UNT Libraries Government Documents Department
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