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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

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

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: April 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department

Analytical Chemistry Division Annual Progress Report for Period Ending December 31, 1959

Description: From Summary: "78,000 analysis were performed in the Thermal Breeder Reactor Projects Analytical Chemistry Laboratory. Principal sample types, methods of analysis used, components determined, and physical measurements required are described."
Date: February 18, 1960
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Current Practices in the Release and Monitoring of I¹³¹ at NRTS, Hanford, Savannah River and ORNL

Description: From abstract: "Release of radioiodine, the chemical and physical forms at the point of release, and changes occurring in form during sojourn in the environment. The monitoring techniques investigated, in use, and most applicable for radioiodine are discussed, and information is presented on the deposition of radioiodine from contaminated clouds and subsequent intake by man."
Date: 196u
Creator: Cowser, K. E.
Partner: UNT Libraries Government Documents Department

Nuclear Superheat Quarterly Project Report: Second Quarter, October-December 1959

Description: From introduction: "This is the second of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

Nuclear Superheat Quarterly Project Report: Third Quarter, January-March 1960

Description: From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: July 1, 1960
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department