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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: AEC research and development report
 Collection: Technical Report Archive and Image Library
Magnetic Force Welding Sintered Aluminum Powder Materials

Magnetic Force Welding Sintered Aluminum Powder Materials

Date: March 1962
Creator: Mills, L. E.
Description: Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Contributing Partner: UNT Libraries Government Documents Department
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
Description: Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor: Final Shielding Design Report

Advanced Test Reactor: Final Shielding Design Report

Date: December 1963
Creator: Howard, J. O.
Description: From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Contributing Partner: UNT Libraries Government Documents Department
A Neutron Absorption Alignment Chart

A Neutron Absorption Alignment Chart

Date: July 30, 1957
Creator: Nisle, Robert G.
Description: From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Contributing Partner: UNT Libraries Government Documents Department
Thermonuclear Project Semiannual Report For Period Ending October 31, 1962

Thermonuclear Project Semiannual Report For Period Ending October 31, 1962

Date: 1963
Creator: Oak Ridge National Laboratory
Description: Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program.
Contributing Partner: UNT Libraries Government Documents Department
Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Date: 1961
Creator: Evans, R. B.; Truitt, J. & Watson, G. M.
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.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Recycle Critical Facility: Final Safeguards Analysis

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
Description: Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

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

Date: March 1961
Creator: Freshley, M. D.
Description: Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Date: October 1964
Creator: Swanberg, F.
Description: Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor Burnout Heat Transfer Tests

Advanced Test Reactor Burnout Heat Transfer Tests

Date: January 1964
Creator: Croft, M. W.
Description: From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Contributing Partner: UNT Libraries Government Documents Department
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