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X-Ray Fluorescence Tables: Program Description
Description:
Report discussing the mechanics of X-Ray and COMBO computer programs.
Date:
July 20, 1964
Creator:
Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
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Report
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Effect of Explosive Impacting on Uranium
Description:
Abstract: The tensile and yield strengths of both cast and wrought uranium discs were substantially increased by explosively impacting them at room temperature and at 375 deg F. However, the room-temperature impacting caused gross damage in the cast material and slight internal damage in the wrought material at the highest impacting pressures. Impacting at 375 deg F, which is just above the brittle-ductile transition temperature for uranium, was the most effective method for increasing the streā¦
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Date:
April 23, 1964
Creator:
Burditt, R. B.; Carey, W. T. & Coughlen, C. P.
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The Application of Data Processing Techniques to a Maintenance Work Control Program
Description:
Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
Date:
December 18, 1963
Creator:
Westbrook, J. D.
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Calculations on U235 Fission Product Decay Chains
Description:
Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Date:
May 1952
Creator:
Faller, I. L.; Chapman, T. S. & West, J. M.
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The Solvent-Extraction Performance of Redox IC Columns (ANL June 1948 Flowsheet) Using Raschig Ring Packing, and Unirradiated Uranium: Redox Technical Study No. 14
Description:
A report which summarizes the performance data obtained from Redox solvent extraction IC Column studies made prior to January 15, 1949 in accordance with conditions of the A.N.L. June 1, 1948, Flowsheet.
Date:
August 22, 1949
Creator:
Hartzell, L. O.; Woodfield, F. W. & Bradley, J. G.
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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
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The Design Study of Fluid Engine Power Systems
Description:
From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date:
April 12, 1963
Creator:
Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
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A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys
Description:
From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date:
March 1964
Creator:
Burns and Roe
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Preliminary Safety Analysis of the Sodium-Deuterium Reactor (SDR)
Description:
From abstract: This work is a safety analysis of the preliminary design of a nuclear reactor.
Date:
March 6, 1959
Creator:
Beusman, Curtis C. & Bernsohn, E.
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Natural Uranium Sodium-Deuterium Reactors: Preliminary Design and Economic Analysis
Description:
From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power.
Date:
February 28, 1959
Creator:
Joseph, L.; Sofer, G. & Goldstein, L.
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The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet
Description:
From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.
Date:
February 14, 1958
Creator:
Yans, F. M.; Donaldson, A. D. & Kaufmann, A. R.
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Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant
Description:
From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
Date:
July 30, 1962
Creator:
Nowak, W. B. & Wessling, B. W.
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Influence of Shield Configuration on Cargo Capacity of Nuclear Powered Ships
Description:
From introduction: The purpose of this report is to make a comparison of cargo carrying capacity and approximate gross revenue of nuclear powered ships.
Date:
January 16, 1956
Creator:
Klepper, O. H.
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Feed Materials Production Center Summary Technical Report: January 1, 1963-March 31, 1963
Description:
This is a summary report of various technical projects relating to uranium.
Date:
May 10, 1963
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Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963
Description:
From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
Date:
October 28, 1963
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Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963
Description:
This report summarizes several reports pertaining to uranium processing.
Date:
July 18, 1963
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Environmental Factors at Proposed Site of Dresden Generating Station of Commonwealth Edison Company
Description:
From introduction: This report is a compilation of the presently available data pertaining to the proposed reactor power plant site which may be used in evaluating the proposed measures for protecting the public from possible radioactive hazards, both during normal operation and under unusual hazards.
Date:
June 15, 1955
Creator:
Kiefer, W. M.; Chiarottino, M. N.; Geue, D. W.; Veras, A. F. & Bonilla, Charles F.
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Final Report to U.S. Atomic Energy Commission: Low-Temperature Heavy Water Plant
Description:
From purpose of report: The primary purpose of this report and its appendices is to transmit to the AEC the principal results of the experimental and engineering work done on the low-temperature process and to describe the factors which led to the designs finally adopted.
Date:
March 15, 1951
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An Inexpensive, Wide Range Gamma Ray Geiger Survey Meter
Description:
From abstract: Detailed information is given on the theory, design, parts specifications and assembly data for a new radiation detector for measurement of ionizing radiations.
Date:
January 4, 1951
Creator:
LeVine, H. D. & DiGiovanni, H. J.
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HASL Aerial Survey System
Description:
Radioactive debris from nuclear detonations may fall out over an extensive area. A rapid evaluation of the distribution of such surface contamination cam be obtained by an aircraft mounted detector. The gamma field measured in the aircraft can be related to the intensity on the ground. The HASL Top Hat'' system measures the radiation intensity, in an aircraft, at any altitude up to 1500 feet. The data are continuously compensated to the reading that would be obtained if the measurements were taā¦
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Date:
July 29, 1957
Creator:
Cassidy, M. E.; Graveson, R. T. & LeVine, H. D.
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Mineralogy of Uranium-Bearing Deposits in the Boulder Batholith, Montana: Final Report, July 1, 1952 to December 31, 1956
Description:
From introduction: This report describes the program of research on mineralogy and petrography of certain uraniferous vein deposits in the Boulder batholith of western Montana.
Date:
October 23, 1957
Creator:
Wright, Harold D.; Bieler, Barrie H.; Emerson, D. O. & Shulhof, W. P.
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10 MWe Sodium Deuterium Reactor Design Report
Description:
From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor.
Date:
1959
Creator:
Davis, Peter J.
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Design Evaluation and Comparison 200 MWe Boiling DāO Pressure Tube Indirect and Direct Cycle Power Reactor Plants
Description:
From foreword: This report is concerned with the investigation of an indirect cycle plant which was the subject of a joint study between Sargent & Lundy and NDA.
Date:
June 30, 1960
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Atomic Energy Commission Reports
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Preparation of Ductile Zirconium
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Fast Ceramic Reactor Development Program Quarterly Report
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IDO
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Mound Laboratory Report for Biological Research
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3
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Feed Materials Production Center Summary Technical Report
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Gamma-Ray Spectrometry of Neutron-Deficient Isotopes Annual Progress Report
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Liquid Metal Fuel Reactor Experiment Quarterly Technical Report
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Nuclear Superheat Meeting Proceedings
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Preparation of Ductile Zirconium Progress Report
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Accurate Nuclear Fuel Burnup Analyses Quarterly Report
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Great Lakes Carbon Corporation Research and Development Division Quarterly Report
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Hanford Atomic Products Operation Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience
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Health and Safety Laboratory Environmental Quarterly Report
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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes
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KAPL Nuclear Physics Section Quarterly Report
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Marysvale Region Study Annual Report
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National nuclear energy series. Division 4, Plutonium Project record
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PM-1 Nuclear Power Plant Program Quarterly Progress Report
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Quarterly Progress Report to the United States Atomic Energy Commission
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1
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Ames Laboratory Semi-Annual Progress Report in Chemistry
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Ames Laboratory, Iowa State University (IS) Series
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Analog Simulation of the Hanford N-Reactor Plant
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Annual Progress Report on Fuel Element Development
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Argonne National Laboratory Biology Division Quarterly Report
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Argonne National Laboratory Quarterly Report
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Clinton Engineer Works Division of Chemical Research and Development Progress Report
1
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Clinton National Laboratory Physics Division Quarterly Report
1
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Electronic Devices for Nuclear Physics Quarterly Report
1
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Fast Ceramic Reactor Development Program Summary Report
1
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1
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Fiscal Year 1972
1
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1
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General Electric Company Reports
1
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Geological report (United States. Bureau of Reclamation)
1
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Graphite Burnout Monitoring
1
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Health and Safety Division Annual Report
1
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In Situ Tracers Project
1
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International Symposium on Developments in Irradiation Capsule Technology
1
1
Irradiation Performance of Thoria-Urania Fuel Materials Quarterly Technical Report
1
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Knolls Atomic Power Laboratory Reports
1
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LA (Series) (Los Alamos, N.M.)
1
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Liquid Metal Fuel Reactor Experiment Annual Technical Report
1
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MTR-ETR Technical Branches Quarterly Report
1
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Mathematics Panel Quarterly Progress Report
1
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Medical and Health Physics Quarterly Report
1
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Mineralogy of Uranium-Bearing Deposits in the Boulder Batholith, Montana Annual Report
1
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Mound Laboratory Biological Research Section Quarterly Report
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NAA Radiation Effects Quarterly Progress Report
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Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor
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Radiolysis of Organic Fluids Annual Progress Report
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Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste
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SL-1 Annual Operating Report
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The H-3 Irradiation Experiment: Irradiation of EGCR Graphite
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The H-4, H-5, and H-6 Irradiation Experiments
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Thin Wall Tubing Tests Using Ultrasonic Shear Waves
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Trace elements investigations report
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United States Bureau of Mines Reports
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WASH (Series)
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