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Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples

Description: This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Partner: UNT Libraries Government Documents Department
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Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.12 Alumel-Chromel Cryogenic Thermocouple

Description: This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Partner: UNT Libraries Government Documents Department
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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

Description: From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: May-July 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Health Physics Division Annual Progress Report, July 31, 1961

Description: Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1961

Description: Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.; Culver, H. N.; Scott, J. L. & Yarosh, M. M.
Partner: UNT Libraries Government Documents Department
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Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Description: Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.
Date: 1961
Creator: Evans, R. B., III; Truitt, J. & Watson, G. M.
Partner: UNT Libraries Government Documents Department
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Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Description: Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
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Large-Scale Slurry-Circulation System, 300-SM

Description: Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.
Date: December 21, 1961
Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.
Partner: UNT Libraries Government Documents Department
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