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Field Operation of a Mobile Reverse Osmosis Pilot Plant

Description: Report that "covers the field operation of a 36-in. diameter pressure-vessel-type reverse osmosis system over a seven month period and the post-operational inspection of the unit and associated hardware" - (p. 1).
Date: May 1969
Creator: Watson, E. R.
Item Type: Report

Filling and Emptying Systems, Low-Lift Locks, Arkansas River Project: Hydraulic Model Investigation

Description: Results of a hydraulic model investigation based on locks in the Arkansas River before the construction of additional locks. "Model studies of the filling and emptying system proposed for use at the low-lift locks in the Arkansas project were conducted to confirm the adequacy of the original design hydraulic system, and to develop, if needed, improvements in the system" (p. 2).
Date: November 1966
Creator: Ables, Jackson H. & Boyd, M. B.
Item Type: Report

Final Design Report: DR-1 Gas Loop

Description: Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
Item Type: Report

Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux

Description: From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Date: March 1, 1965
Creator: Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.
Item Type: Report

Final Report: The Cesium-137 Power Program

Description: From introduction: The technology of isotopic power generation, though recent, is a logical extension of the search for power from the atom. Controlled fission of uranium utilizes only a fraction of the total energy made available from this nuclear process.
Date: May 1964
Item Type: Report

Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Item Type: Report

Final Safety Analysis Report: SNAP III Thermoelectric Generator

Description: From summary: An analysis has been performed to determine the ability of the fuel container to withstand the various thermal, mechanical and chemical forces imposed upon the generator by vehicle failures. Where theoretical analysis was impossible, and where experimental evidence was desired, capsules and generators were tested under simulated missile-failure conditions. Thus, the safety limits of SNAP III in a satellite application were defined.
Date: June 1960
Creator: Hagis, W. & Dix, George P.
Item Type: Report

Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A

Description: From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.
Date: February 1962
Creator: Brooks, Phillip M. & Keegan, James J.
Item Type: Report

Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C

Description: From introduction: The primary objectives in designing a nuclear safe radiostrontium generator are: continuous absolute containment of the radiostrontium fuel, which is a relatively insoluble and chemically stable fuel compound, and biological shielding of the direct radiation from the heat source. This report evaluates the safety aspects of a prototype Strontium-90 fueled generator which will be utilized by the U.S. Navy to power and unattended automatic meterological station.
Date: 1962
Creator: Brooks, Phillip & Keegan, James J.
Item Type: Report

Fire Tests of Precast Cellular Concrete Floors and Roofs

Description: From Abstract: "The results of an investigation of lightweight, precast cellular concrete planks are given. Fire tests were made of two floor and five roof specimens made up of these planks. Variables, included density of the cellular concrete, thickness and span of the planks, reinforcement, and cover for the latter."
Date: April 12, 1962
Creator: Ryan, J. V. & Bender, E. W.
Item Type: Report

Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.
Item Type: Report