Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending March 31, 1963

Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending March 31, 1963

Date: July 23, 1963
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending September 30, 1962

Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending September 30, 1962

Date: 1962
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Date: [1963-09-30..1964-01-29]
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Date: March 1961
Creator: Sharp, R. E.
Description: Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Contributing Partner: UNT Libraries Government Documents Department
Army Gas-Cooled Reactor Systems Program: Semiannual Progress Report, 1 January Through 30 June 1961

Army Gas-Cooled Reactor Systems Program: Semiannual Progress Report, 1 January Through 30 June 1961

Date: August 10, 1961
Creator: Aerojet-General Corporation
Description: Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
Contributing Partner: UNT Libraries Government Documents Department
Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Date: March 1959
Creator: Kaiser Engineers
Description: Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant.
Contributing Partner: UNT Libraries Government Documents Department
Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant

Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant

Date: August 1958
Creator: Kaiser Engineers
Description: Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations.
Contributing Partner: UNT Libraries Government Documents Department
Heat Transfer in an Annulus with Asymmetric Heating

Heat Transfer in an Annulus with Asymmetric Heating

Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. B. & Reynolds, William C., 1933-2004
Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Contributing Partner: UNT Libraries Government Documents Department
The Oak Ridge National Laboratory Gas-Cooled Reactor: Plant Design, Number 3

The Oak Ridge National Laboratory Gas-Cooled Reactor: Plant Design, Number 3

Date: January 4, 1958
Creator: Oak Ridge National Laboratory
Description: Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.
Contributing Partner: UNT Libraries Government Documents Department
The Oak Ridge National Laboratory Gas-Cooled Reactor: Plant Design, Number 2

The Oak Ridge National Laboratory Gas-Cooled Reactor: Plant Design, Number 2

Date: April 1, 1958
Creator: Oak Ridge National Laboratory
Description: Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.
Contributing Partner: UNT Libraries Government Documents Department
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