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  Partner: UNT Libraries Government Documents Department
 Collection: Technical Report Archive and Image Library
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
Design Report for Nuclear Merchan Ship Reactor Pressurized Water Loop at Oak Ridge National Laboratory Research Reactor

Design Report for Nuclear Merchan Ship Reactor Pressurized Water Loop at Oak Ridge National Laboratory Research Reactor

Date: 1963
Creator: Dudley, I. T.; Tidwell, D. E. & Trauger, Donald B.
Description: Report describing a pressurized water loop that was constructed for use in the Maritime Reactor Program. The report also includes the operational experience of using the device. Appendices begin on page 48.
Contributing Partner: UNT Libraries Government Documents Department
An Investigation of the Instantaneous and Creep Buckling of Initially Out-of-Round Tubes Subjected to External Pressure

An Investigation of the Instantaneous and Creep Buckling of Initially Out-of-Round Tubes Subjected to External Pressure

Date: 1963
Creator: Corum, J. M.
Description: Report regarding a method for predicting the instantaneous and creep buckling characteristics of tubes to lateral external pressures using a small sample of 8.0-in.-o.d. stainless steel tubes. The report includes the development and application of buckling theories. Appendix begins on page 71.
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
Report of the Thirty-Sixth National Conference on Weights and Measures: Attended by Representatives from Various States

Report of the Thirty-Sixth National Conference on Weights and Measures: Attended by Representatives from Various States

Date: December 10, 1951
Creator: United States. Bureau of Standards.
Description: Report of the thirty-sixth National Conference on Weights and Measures.
Contributing Partner: UNT Libraries Government Documents Department
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

Date: June 1961
Creator: Todd, R. H.
Description: This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
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
Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

Date: March 1963
Creator: Ebasco Services Incorporated
Description: From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."
Contributing Partner: UNT Libraries Government Documents Department