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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

Description: The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date: November 1, 1961
Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Port Survey of the State of New York

Description: Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date: November 1961
Creator: Ebasco Services Incorporated
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Site Attenuation

Description: Abstract: Site attenuation is a measure of performance of an open test site used at frequencies below about 1 GHz for antenna calibration and equipment emission and susceptibility testing. These sites typically consist of a large, obstruction-free ground plane and the hemisphere above it. Site attenuation of an ideal site is calculated and compared to data measured using the 30 m by 60 m NBS ground screen.
Date: November 1985
Creator: FitzGerrell, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of Materials for Supercritical-Water Reactor

Description: Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.
Date: November 27, 1953
Creator: Udy, Murray C. & Boulger, Francis W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program Relating to Civilian Applications During October, 1958

Description: A report pertaining to the thermal-conductivity and electrical-resistivity measurements of uranium encapsulated in zircaloy-2 and surrounded with NaK as a heat-transfer material which is not in agreement with results obtained from unclad uranium.
Date: November 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

Description: From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ pa… more
Date: November 14, 1952
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor

Description: Technical report covering the functions of the Oak Ridge reactor, difficulties encountered with cartridge failures in the Oak Ridge reactor, and possible solutions including the incorporation of leak detection systems into the design of the reactor.
Date: November 3, 1968
Creator: Chernick, J. & Kaplan, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aerial Gamma Ray and Magnetic Survey, Volume 2. Final Report: Elk City Quadrangle of Idaho/Montana

Description: Second volume of a report documenting a high-sensitivity airborne radiometric and magnetic survey of the Elk City quadrangle including a detailed geologic summary, interpretation report, standard deviation maps, pseudo-contour maps, interpretation maps, flight line and geologic base map, and individual corrected profiles.
Date: November 1979
Creator: EG & G GeoMetrics
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Description: Technical report evaluating solvents for use in the extraction of uranium from Mallinckrodt type ore feeds. Re-evaluates the Mallinckrodt process in the light of the more recent solvent extraction development that has been carried out at various AEC sites.
Date: November 6, 1950
Creator: Runion, T. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

Description: From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NURE Aerial Gamma Ray and Magnetic Reconnaissance Survey, Thorpe Area, Volume 1 - Narrative Report: Newark (NK 18-11) Quadrangle

Description: Final report documenting a high-sensitivity airborne radiometric and magnetic survey of the Newark quadrangles including the survey description, specifications, data processing methods, interpretation methods, and regional geologic review.
Date: November 1977
Creator: LKB Resources, Inc.
Item Type: Refine your search to only Report
Location: None
Partner: UNT Libraries Government Documents Department
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