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Acoustic Flowmeter Prototype Evaluation Tests

Description: Summary: "Prototype tests of an acoustic flowmeter system were made in a 24-ftdiam power penstock at Oahe Dam to evaluate the system prior to permanent installation in the outlet works at Summersville Dam. Comparative discharge measurements included acoustic, penstock pressure-momentum (Gibson), turbine model test ratings, scroll-case pressure differential (Winter-Kennedy flowmeter), and surge tank volume changes. The acoustic flowmeter measurements were very consistent and many of the comparisons were within 1%. The location of the measuring section for a single-path acoustic flowmeter must be selected to give a known or measurable relation between the flow pattern of the whole section and that along the acoustic path" (p. xi).
Date: January 1968
Creator: Pickett, Ellis B.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Description: From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Description: First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Description: Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date: March 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Test Reactor Burnout Heat Transfer Tests

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

Advanced Test Reactor: Final Shielding Design Report

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."
Date: December 1963
Creator: Howard, J. O.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Test Reactor Servo Regulator Rod Test Program

Description: From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advanced Test Reactor Turbo Report

Description: From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date: January 1964
Creator: Turner, Robert A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Advances in Coal Spectrometry: Absorption Spectrometry

Description: Report from the U.S. Bureau of mines discussing the use of infared and ultraviolet-visible spectrometry to study the structure of coal and coal extracts.
Date: 1967
Creator: Friedel, Robert A.; Retcofsky, H. L. & Queiser, J. A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

AEC Group Shelter

Description: Report regarding the study of an underground group-shelter meant to protect against nuclear blasts, radiation, and fallout. The report presents a design for such a shelter, the minimum requirements that such a shelter should meet, a description of its facilities, illustrations, and an operating manual.
Date: January 1960
Creator: Holmes & Narver
Item Type: Report
Partner: UNT Libraries Government Documents Department

Aerial Photographs in Geologic Interpretation and Mapping

Description: Abstract: Aerial photographs today are widely used to obtain both qualitative and quantitative geologic information; vertical aerial photographs are used almost to the exclusion of other types. Techniques and procedures described herein relate primarily to vertical photography.
Date: 1960
Creator: Ray, Richard G.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Aerial Radiological Monitoring System

Description: From abstract: "This report describes the Aerial Radiological Measuring System (ARMS-II) operated by EG&G, Inc., for the Division of Biology and Medicine, U. S. Atomic Energy Commission."
Date: October 1967
Item Type: Report
Partner: UNT Libraries Government Documents Department