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Stability of Florothene Under Exposure to Gamma Radiation

Description: The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding

Description: Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.
Date: July 25, 1955
Creator: Adley, F. E. & Gill, W. E.
Partner: UNT Libraries Government Documents Department
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A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media

Description: Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date: August 10, 1953
Creator: Adley, F. E.; Scott, R. H. & Gill, W. E.
Partner: UNT Libraries Government Documents Department
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Chemical Research Section Progress Report for January 1950

Description: The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Partner: UNT Libraries Government Documents Department
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Program Study Report Plutonium Fuel Cycle

Description: From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
Partner: UNT Libraries Government Documents Department
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A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Description: Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Pap… more
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
Partner: UNT Libraries Government Documents Department
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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Partner: UNT Libraries Government Documents Department
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Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

Description: It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stabi… more
Date: December 23, 1959
Creator: Allen, C. W.
Partner: UNT Libraries Government Documents Department
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Some Comments on the Selection of Operating Temperatures for DPR

Description: The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser ex… more
Date: November 16, 1953
Creator: Altmann, Manfred.
Partner: UNT Libraries Government Documents Department
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Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

Description: The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Physical Properties of Neutralized Zirflex Waste

Description: Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.
Date: June 8, 1959
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Regeneration of Silver Reactors

Description: A study of the variables involved in regeneration was undertaken to determine means of improving the regeneration efficiency and increasing the useful life of a reactor. Information gained from regeneration studies on a 4-inch-diameter by 8-foot-high column indicates that the present regeneration procedure is optimum as to quantity, concentration, and rate of addition of regenerant solution. It appears feasible to restore a plugged reactor by washing off all the silver nitrate from the packing … more
Date: December 27, 1955
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

Description: This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department Analytical Laboratory Manual

Description: The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.
Date: June 1959
Creator: Analytical Laboratory Manufacturing Operation
Partner: UNT Libraries Government Documents Department
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Potential Nitrate Decomposition High Level Waste Storage

Description: It is recommended that self-concentration of Purex wastes should not be started until much more complete knowledge is obtained of the conditions and reactions in these wastes. The presently planned tests in the Semi-Works will be a practical demonstration of the problems but will be of little value on the initial Purex wastes as these tests are being run almost concurrent with the filling of the first Purex storage tank.
Date: April 27, 1955
Creator: Anderson, C. R.
Partner: UNT Libraries Government Documents Department
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Partner: UNT Libraries Government Documents Department
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The formation of chemical film deposits on aluminum surfaces

Description: From abstract: "The purpose of this investigation was to establish basic rates of formation of chemical films deposited on aluminum surfaces from water flowing over such surfaces. It was desired to obtain specific information, within certain ranges, as to the influence of temperature, water velocity, and type of aluminum on the rate of film formation."
Date: February 1952
Creator: Andrews, R. V.
Partner: UNT Libraries Government Documents Department
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