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P-V-T Relationships of BF₃ Gas

Description: Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date: July 30, 1960
Creator: Smith, C. R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report - April 1960, Chemical Technology Division

Description: Progress is reported on chemical engineering research, solvent extraction, fuel cycle development, thorium studies, ion exchange, reactor fuel processing, solvent extraction, and waste processing.
Date: July 28, 1960
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Storm Data and Unusual Weather Phenomena, Volume 2, Number 6, June 1960

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: July 27, 1960
Creator: United States. Weather Bureau.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Volatility Pilot Plant - Hazards Review Report

Description: The ORNL Fluoride Volatility process for the dissolution of Zr-U fuel elements in Building 3019 is described, and possible hazards and their control are discussed.
Date: July 26, 1960
Creator: Milford, R. P.; Carr, W. H.; Cathers, G. I.; Horton, R. W.; Mann, S.; Miles, F. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plowshare Program : Peaceful Uses for Nuclear Explosives

Description: The concept of thermonuclear explosives as a potentially cheap and almost inexhaustible energy source for mankind's non military needs has for several years been under active consideration at the Lawrence Radiation Laboratory. Many of the proposed peaceful applications involve underground nuclear explosions, and several experiments at the AEC Nevada Test Site have provided valuable insight into the phenomenology of such explosions. Among the possible uses currently under consideration are excav… more
Date: July 25, 1960
Creator: Lombard, David B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PCTR Measurement of EGCR Control Rod Worth

Description: This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, v… more
Date: July 20, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study of Heat and Mass Transfer to Uninsulated Liquid Oxygen Containers

Description: The wide use of liquid oxygen as an oxidant in rocket engines has resulted in an increased interest in low-temperature heat transfer. Storage tanks for this type of application, being uninsulated, contain a boiling-liquid low-temperature sink, which is susceptible to environmental heat inputs and subsequent liquid loss by vaporization. Such losses are difficult to predict due to the complex combination of ambient conditions which exist, and the lack of knowledge concerning their combined effect… more
Date: July 20, 1960
Creator: Holten, David Charles
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Project Cowboy : Physical Properties of Salt Samples

Description: The purpose of Project Cowboy was to investigate the seismic signals generated by chemical explosions in underground cavities, with particular emphasis on the possibility of decoupling of these signals from the surrounding media. The project site was the Carey Salt Company salt mine, located approximately five miles west of Winnfield, Louisiana. The tests were run during fiscal year 1960. This report presents the results of tests performed on specimens from the samples of salt taken in the area. more
Date: July 15, 1960
Creator: Guido, Raymond S. & Warner, Stanley E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Grade Zircaloy-2 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor-Grade Zircaloy-4 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Sheet and Strip Material

Description: Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Wire Material

Description: Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Zircaloy-4 Sheet and Strip Material

Description: Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Zircaloy-4 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Zircaloy-4 Wire Material

Description: Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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