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Design and economic study of hot off-gas storage system

Description: From introduction: "One of the most important factors which must be considered in the chemical processing of spent fuel elements is the safe and economic disposal of gaseous radioactive fission product wastes given off in the fuel element dissolution operation. For this reason work is underway at ORNL to study the various gas disposal methods that might be used to handle the radioactive fission product gases, krypton, xenon, and iodine."
Date: December 20, 1957
Creator: Johnson, C. S. & Carter, T. J.
Partner: UNT Libraries Government Documents Department
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Drying of Charcoal Used for Adsorption of Gaseous Fission Products from Homogeneous Reactors

Description: In homogeneous nuclear reactors significant quantities of radioactive inert gaseous fission products must be separated from the fuel solution for disposal. The present disposal scheme, which is employed on the HRT, is to pass the mixture of fission product gases and oxygen through a charcoal adsorption bed. the oxygen passes through the bed relatively un-adsorbed, but the radioactive inert gases are adsorbed and are displaced from the bed bed very slowly giving the gases a much greater residenc… more
Date: December 20, 1957
Creator: Funderburg, J. M. & Moss, L. I.
Partner: UNT Libraries Government Documents Department
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Eddy Current Detection of Al-Si Penetrations in Canned Slugs

Description: From abstract: "An instrument for detecting aluminum-silicon alloy penetrations in the aluminum jacket of fuel slugs is described. The instrument is of the eddy current type and the sensing element is a small probe that does not touch the specimen under inspection. Al-Si inclusions 0.020 inch in diameter that penetrate to within 0.005 inch of the can surface can be detected. The response of the circuits is such that a slug 8 inches long can be scanned in 45 seconds."
Date: December 1957
Creator: Robinson, Richard C. & Ross, John D.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment (Phase 1C): Supplement to LMFRE Reference Design Report

Description: This supplement describes a number of modifications to the Liquid Metal Fuel Reactor Experiment (LMFRE), including (1) engineering design changes to achieve economies in the original reference design, and (2) a revised cost estimate that reapportions the various construction, research and development, and operating costs in accordance with procedures established by the Atomic Energy Commission.
Date: December 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: August-October 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
Partner: UNT Libraries Government Documents Department
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Plating Thickness Tester

Description: An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
Partner: UNT Libraries Government Documents Department
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Reactor Physics Primer

Description: Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date: November 15, 1957
Creator: Lockwood, E. H.
Partner: UNT Libraries Government Documents Department
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Zircex Kinetics And Uranium Loss Study

Description: "A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented."
Date: November 13, 1957
Creator: Carter, Jr, T. J. & Stone, R. A.
Partner: UNT Libraries Government Documents Department
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Precise Vapor Pressure Measurement At High Temperature

Description: "An apparatus using a silica Bourdon gage is described for the measurement of vapor pressures or dissociation pressures with an accuracy of 0.1 mm and 0.1 deg C up to maximum pressures of atmospheric or beyond and maximum temperatures of 650 to 1250 deg C. The method is applicable to corrosive substances, to substances whose vapor pressure is sensitive to slight changes in composition, and to substances difficult to purify of volatile contaminants which affect the vapor pressure."
Date: November 1, 1957
Creator: Machol, Robert E.
Partner: UNT Libraries Government Documents Department
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Summary of the Spert-I, -II, and -III reactor facilities

Description: Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date: November 1, 1957
Creator: Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Preliminary Hazards Evaluation for the Use of Sodium in the BNL Four-Inch Loop

Description: The contemplated use of sodium in place of bismuth in the secondary system of the Four-Inch Loop at Brookhaven National Laboratory requires a re-evaluation of the loops design. This report covers those design changes deemed necessary for safe operation of the system. It also includes an evaluation of the possible hazards involved and methods of coping with them. No attempt is made here to cover the hazards of sodium-bismuth reaction.
Date: October 1957
Creator: The Babcock and Wilcox Company
Partner: UNT Libraries Government Documents Department
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Solvent Extraction Concentration of Certain Rare Earths in Yttrium

Description: Abstract: A procedure is given for the concentration of gadolinium, dysprosium, and samarium in yttrium oxide by extraction of the thiocyanates with tributyl phosphate. Concentration of these elements up to 80-fold was obtained. Results are given on the effects of ammonium thiocynate and tributyl phosphate concentrations, as well as pH, temperature and sample size on the separation. Analyses of standard yttrium oxide samples after concentration of these rare earths are in good agreement with re… more
Date: October 1957
Creator: Eberle, Allan R. & Lerner, M. W.
Partner: UNT Libraries Government Documents Department
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