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Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951

Description: The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The … more
Date: January 9, 1952
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, William B.
Item Type: Refine your search to only Report
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The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor

Description: Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]
Date: January 9, 1953
Creator: Reed, James
Item Type: Refine your search to only Report
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Determination of Traces of Uranium Metal by Decomposition of the Hydride

Description: Two methods were developed for the determination of uranium metal in UF3 with other fluoride compounds. A simplified method of determination which has a relatively high degree of precision (coefficient of variation 2 per cent) is carried out by decomposing the hydride in an atmosphere of carbon dioxide and subsequently measuring the hydrogen over an aqueous solution of potassium hydroxide. The ignition of the hydride in an atmosphere of oxygen and volumetric measurement of the water at reduced … more
Date: November 9, 1955
Creator: Meyer, A. S., Jr.; McDowell, B. L. & White, J. C.
Item Type: Refine your search to only Report
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Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Item Type: Refine your search to only Report
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The HRT Refrigerating System

Description: The HRT refrigeration system was designed to use Freon-11 (CCI3F) as the refrigerant material in the secondary loop. A Van de Graaff irradiation of this material indicated that serious corrosion problems were probable if Freon were used in the proposed metal system. A survey was made of candidate refrigerants, and Amsco 125-82 and triethyl phosphate were selected for irradiation and physical-property determinations.
Date: January 9, 1957
Creator: Silverman, M. D.
Item Type: Refine your search to only Report
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Production of Fuel Assemblies for the Materials Testing Reactor Mock-Up Critical Experiments

Description: Technical report outlining the fabrication of twenty-five fuel assemblies and three shim-safety rod fuel sections for use in the Materials Resting Reactor Mock-Up Critical Experiments. Results show that two of the assemblies exceeded tolerance in a few of the key dimensions, but were considered acceptable and as a consequence, production was carried out with no rejects. [From Abstract]
Date: April 9, 1951
Creator: Smith, C. D.; Drosten, F. W. & Kerze, F., Jr.
Item Type: Refine your search to only Report
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Radiation Hazards from Recycled Reactor Fuel

Description: The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U-233 and plutonium fuels where the presence of U-232 and the heavier isotopes of plutonium contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U-233 and Pu-239. This report summarizes present knowledge of the radiation hazards associated with recycled fuel and the addi… more
Date: June 9, 1959
Creator: Arnold, E. D.
Item Type: Refine your search to only Report
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Shielding Reactor Corrosion Studies

Description: Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Item Type: Refine your search to only Report
open access

Specifications for Fuel Assemblies for Core I of the Experimental Gas-Cooled Reactor

Description: These specifications for the fuel assemblies for Core I of the Experimental Gas-Cooled Reactor (EGCR) have been developed for use in procuring the first core loading. A fuel assembly for EGCR consists of a cluster of seven cylindrical fuel elements spaced and supported within a graphite sleeve. Each fuel element consists of a stainless steel tube containing a column of hollow UO2 pellets and having a spacer brazed at the midsection to control the spacing between fuel elements in a cluster. A ma… more
Date: December 9, 1960
Creator: Coobs, J. H.; Wick, E. A. & Evans, R. M.
Item Type: Refine your search to only Report
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Ultraviolet Spectrophotometric Determination of Osmium Tetroxide in CHCl3 by G. Goldstein

Description: A method was developed for the determination of osmium by measuring the absorbancy of osmium tetroxide in CHCl3. The osmium is first oxidized to the octavalent state and the osmium tetroxide which is formed is extracted selectively with CHCl3. The ultraviolet absorption spectrum of OsO4 in CHCl3 has a series of absorption bands with peak absorbancies at 282. 289, 297, 304 and 312 mu, and molar absorbancy indices of 1870, 1760, 1640, 1400 and 1000, respectively. For each wavelength the optimum c… more
Date: June 9, 1959
Creator: Menis, Oscar
Item Type: Refine your search to only Report
open access

Unit Operations Section Monthly Progress Report July 1959

Description: A Lucite model of a multi-stage countercurrent hydroclone solvent extraction apparatus has been constructed and tested with Amsco-water. The diffusivity of Cs 134 tracer in aqueous chloride solution was measured to check the performance of the capillary diffusivity measuring system. The experimental data from four Druhm runs showed that 1/8in. thick graphite liners are usable for reactor temperatures above the boiling point of sodium.
Date: October 9, 1959
Creator: Bresee, J. C.; Haas, P.A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
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