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Heat Treatment and Machinability of Beryllium Rod

Description: Purpose: "The purpose of this investigation was to determine whether or not the machinability of extruded beryllium rod could be improved by appropriate heat treatment. It was thought that this could be accomplished in the extruded Be rod by recrystallization without further growth of these grains. This should impart a certain degree of ductility to the metal. The investigations was divided into two parts: Part I - Heat Treatment of Beryllium Rod; Part II - Machinability of Beryllium Rod."
Date: February 19, 1946
Creator: Norhaft, P. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of Los Alamos and Pueblo Canyon for Radioactive Contamination and Radio Assay Tests Run on Sewer-Water Samples and Water and Soil Samples Taken From Los Alamos and Pueblo Canyons

Description: "Report of the Survey of Los Alamos and Pueblo Canyon for radioactive contamination and radioassay tests run on sewer water samples and water and soil samples taken from Los Alamos and Pueblo Canyons." The objective of this report was to determine the extent and sources of radioactive contamination in the areas studied.
Date: February 20, 1947
Creator: Kingsley, William H.; Fox, Alvin; Tribby, J. F. & Doner, Elmer
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluated Neutron Cross Sections for Tritium

Description: From foreword: Evaluation of the experimental data on the light isotopes, hydrogen through beryllium, was initiated by LASL in mid-1963. Since the data compilations available were completely inadequate for the task at hand, the tedious program of compiling and plotting was undertaken. As the work progressed an attempt was made to eliminate many of the obvious errors and inconsistencies found in the literature and existing compilations.
Date: February 1965
Creator: Stewart, Leona
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Hydrogeochemical and Stream Sediment Reconnaissance in the San Juan Mountains, Southwest Colorado

Description: From 1995 sites in the San Juan Mountains area, 1706 water and 1982 sediment samples were collected during June-July 1976 and analyzed for uranium. The area includes the southern third of the Colorado mineral belt which has yielded rich ores of gold, silver, copper, lead, zinc, and molybdenum. The broadly domed mountains are capped by 2500 m of Tertiary volcanics, deeply eroded to expose a Precambrian crystalline core. Adjacent plateaus underlain by Mesozoic sedimentary rocks were included in t… more
Date: February 1977
Creator: Maxwell, James C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Hydrogeochemical and Stream Sediment Reconnaissance in Southwestern Montana

Description: From introduction: This report presents data gathered in a Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) conducted by the Los Alamos Scientific Laboratory (LASL) in southwestern Montana. The HSSR was initiated by the US Department of Energy (DOE) to outline areas favorable for uranium exploration by examining uranium concentrations in natural waters and stream sediments.
Date: February 1978
Creator: Broxton, David E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Method of Cleaning Plutonium Metal Samples for Analysis

Description: The usual method of removing surface oxide from plutonium metal samples, by electrolytic cleaning in a mixture of ethylene glycol and phosphoric acid, is not satisfactory for preparing samples for oxygen determination. Samples prepared in this way give erratic oxygen values. This report describes a new method of electrolytic cleaning, using a 20 ~ aqueous potassium carbonate solution as the electrolyte. The sample is placed in a rotating tantalum cup which is made the anode. Electrolysis for tw… more
Date: February 2, 1953
Creator: Smiley, William G. (William Gooding), 1915-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Determination of Oxygen in Plutonium by the Capillary Trap Method

Description: A new method for the determination of O/sub 2/ in metals is described. The sample is dropped into molten Pt in a graphite crucible. The oxide in the sample reacts with C to form CO, which is swept out by a stream of argon at atmospheric pressure. The CO is oxidized to CO/sub 2/, which is condensed in a capillary trap and measured with a capillary manometer. The apparatus is sensitive to 0.3 mu g of O/sub 2/, and routine 50-mg Pu samples give a standard deviation of 7 ppm or 0.35 mu g. Pu sample… more
Date: February 1, 1953
Creator: Smiley, William G. (William Gooding), 1915-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Modification of the Norelco Diffractometer for the Identification of Phases in Metallographic Specimens

Description: A modification of the specimen support for the Norelco diffractometer permits X-ray diffraction studies to be made of specimens prepared for metallographic examination. The unit has been successfully used to identify phases present in specimens of plutonium-uranium alloys.
Date: February 25, 1952
Creator: Stambaugh, C. K. & Whyte, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculations of the Critical Mass of UF6 as a gaseous Core, with Reflections of D2O, Be and C

Description: A class of critical assemblies has been considered in which the core consists of an oralloy bearing gas at more or less standard pressure and temperature and the reflector is an efficient moderator with a small thermal capture cross section. Age and diffusion theory have been applied to compute the probability that a fast neutron is thermalized by the reflector and them captured by the core. It is first assumed that fast or epithermal neutrons do not interact wit the core and it is later shown … more
Date: February 1955
Creator: Bell, George I., 1926- & Goldstein, Max
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation of Uranium-Columbium Alloys by Bomb Reduction

Description: High purity, homogeneous alloys of uranium and columbium have been produced by adding powdered columbium metal or columbium/sub 2/O/sub 5/ to a regular reduction charge. Alloys up to 20.0 at.% columbium were produced. The preparation of the alloys, some of their properties, and casting results are described.
Date: February 1952
Creator: Hayward, B. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A High Volume Casting Furnace for Plutonium

Description: A high-vacuum casting furnace with an internal diameter of 15 inches has been designed, fabricated, and installed at LASL. The furnace was designed to accommodate casting crucibles up to 7 inches OD; however with a larger diameter heating element, casting crucibles up to 9 inches could be accommodated. This report describes the basic features of the furnace and presents engineering drawings of both the furnace and the furnace box.
Date: February 17, 1953
Creator: Anderson, J. W. & Thomas, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy Distribution of Fast Neutron Beam

Description: Experimental techniques are described for the spectral measurement of a collimated fast neutron beam. A hydrogen filled cloud chamber, proton recording nuclear plates, and threshold fission foils were used as neutron detectors in the measurements. As an application of the above technique, the energy distribution and absolute flux of the fast neutron beam emerging from port 5W of the Los Alamos fast rector has been measured from 0.1 Mev to 18 Mev. The result show a spectral curve possessing a ma… more
Date: February 15, 1951
Creator: Nereson, Norris G., 1918-2007
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Hazards Summary for the Proposed Los Alamos Omega West Reactor

Description: The proposed Los Alamos Omega West Reactor is designed to be a research tool delivering a maximum neutron flux of approximately 5 x 10/sup 13/ n/sec/cm/ sup 2/ at its maximum operation power level of 5 megawatts. Solid fuel elements of the type developed for the Materials Testing Reactor will be utilized. Cooling will be accomplished with circulating demineralized water and evaporative coolers. Experimental facilities will include numerous horizontal ports, two of which will incorporate built-i… more
Date: February 1954
Creator: Jurney, Edward Thornton, 1921-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calcium Oxalate Carrier Precipitation of Pu

Description: This technical report describes a plant-scale procedure for concentrating plutonium and americium in slag and crucible (metal reduction residues) and other recovery solutions by a calcium oxalate carrier precipitation Conclusions from exploratory laboratory tests on the variables affecting the efficiency are included.
Date: February 25, 1954
Creator: Maraman, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the La Junta NTMS Quadrangle, Colorado, Including Concentrations of Forty-Three Additional Elements

Description: This report provides uranium and other elemental data resulting from the Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the La Junta quadrangle, Colorado.
Date: February 1979
Creator: Purson, John D. & Warren, Richard G.
Item Type: Refine your search to only Report
Location: None
Partner: UNT Libraries Government Documents Department
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Fabrication Procedure For RaLa Source Fuel Rods

Description: A new method to procure RaLa sources was proposed by Group CMR-10, Los Alamos Scientific Laboratory. This method depended upon irradiation of small-diameter U235 wire in the Materials Testing Reactor, Arco, Idaho. A procedure for cladding and sealing U235 wire in stainless steel tubing, by drawing, plugging the tube ends, and welding, was developed, tested, and proved to be satisfactory.
Date: February 15, 1956
Creator: Hockett, J. E.; Duncan, J. D.; Doll, D. T. & Taub, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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