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The Spontaneous Fission of Plutonium-240

Description: The spontaneous fission rate of plutonium-240 has been redetermined and found to be 1.51 X 106 events/g/hr.
Date: April 15, 1953
Creator: Kinderman, E. M.
Partner: UNT Libraries Government Documents Department
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Ground Level Concentrations in the Vicinity of a 185 ft Stack

Description: Field tests were conducted to measure short-period pollutant concentrations at several stack heights during conditions of marked atmospheric instability and low wind speeds. The source was a mechanical smoke generator located at the 185-ft level of a tower.
Date: April 20, 1953
Creator: Shorr, B.
Partner: UNT Libraries Government Documents Department
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Slug Manipulator

Description: A manipulator designed to support an irradiated slug at the bottom of the viewing basin, so that an operator could view it through a binocular telescope and be able to see all surfaces, was designed. Hydraulic power, using water, operates the manipulator and gears.
Date: April 30, 1953
Creator: Slind, M. T.
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steels in Purex Acid Concentrators

Description: The corrosion resistance of four types of austenitic stainless steels to Purex process first and second acid concentrator bottoms was determined. Although the compositions of the two solutions were very similar, tests in simulated solutions of both compositions were conducted to strengthen the basis for the conclusions which were to be made.
Date: April 23, 1953
Creator: Sanborn, Kenneth L.
Partner: UNT Libraries Government Documents Department
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Thermal Spikes and Uranium Instability

Description: Thermal spikes occurring during the life of a slug in a pile cause a momentary destruction of the original configuration of atoms in the metal. This process occurs at such a rate that in a thermal neutron flux of 10(13) neutrons per square centimeter per second each atom in the metal will be subject to temperatures above the melting point of uranium every 40 minutes.
Date: December 10, 1952
Creator: Last, G. A. & McLachlan, D., Jr.
Partner: UNT Libraries Government Documents Department
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Outgassing Tests of Uranium Slugs

Description: During the canning of slugs for Production Test 313-105-3-M, a high number of rejects were caused by gas voids in the A1-S1 bonding layer. Since the heat treatment of the slugs in a molten salt bath resulted in a chemically altered surface, an investigation was made to determine the volume of gas evolved from salt-bath heat-treated slugs as compared to other types of slugs. This test was designed as a preliminary test to determine if there were a significant differences.
Date: May 27, 1953
Creator: Johnson, H. A.
Partner: UNT Libraries Government Documents Department
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Technical Activities Report for April 1953

Description: Two xenon extraction runs were made this month. It appears that a small design change in Trap #2 will be necessary so that a dry ice-trichloroethylene slurry can be used for coolant rather than liquid freon. For each of the runs this month the enriched generator was exposed for four hours in the est pile operating at 100 watts. A period of eight hours for cooling and xenon builidup was allowed before the collection and separation runs were started.
Date: May 4, 1953
Creator: Faulkner, J. E.; Davenport, D. E. & Duvall, G. E.
Partner: UNT Libraries Government Documents Department
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The Identification of the Angular Inclusions Present in Rolled Uranium

Description: Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusions from the matrix metal.
Date: May 15, 1953
Creator: Scott, F. A.
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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A Hanford Works Vacuum System

Description: The remodeling, fabrication, and instrumentation of a high vacuum system are described. The faults encountered with the old system and their solution are outlined. Tests were made on diffusion pump oils and on the reduction of pump oil back diffusion. The measurement of high vacuum pressures by a cold cathode ionization gage at various points on a vacuum system are discussed.
Date: May 28, 1953
Creator: Holdreth, N. T.
Partner: UNT Libraries Government Documents Department
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The Use and Calibration of Scintillation Counter--Model Y

Description: Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure operation at a preferred energy threshold of 0.1 Mev and an arbitrarily fixed counting yield of 3.36% for Cs-Ba-137. Partial pulse height discrimination against U 237 is also accomplished.
Date: August 1, 1953
Creator: Brauer, F. P. & Leboeuf, M. B.
Partner: UNT Libraries Government Documents Department
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Electrical Resistance Measurements of an Irradiated Uranium Sample

Description: The results of electrical resistance measurements have been used as a means of following changes occurring in metals due to irradiation. The electrical conductivity is sensitive to changes in composition and to cold-work or structure damage. In an anisotropic metal, such as uranium, the director of measurement also influences to some extent the values obtained. For these reasons it is essential to use the same material, and if possible the same piece of material, in comparing the electrical properties before and after irradiation. This report is a description of the measurements made on pieces of the same uranium rod before and after an exposure of approximately 150 MWD/T. The results, while preliminary in nature and dealing only with one sample and exposure level, provide data for which a comparison may be made of the electrical resistivity of irradiated and non-irradiated uranium metal.
Date: June 8, 1953
Creator: Kemper, Robert S. & Boyd, C. L.
Partner: UNT Libraries Government Documents Department
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Radioactive Particle Fallout in the Hanford Environs from Nevada Nuclear Explosions Spring-1953

Description: Various organizations in the Biophysics Section of the Radiological Sciences Department participated in evaluating local radioactive particle fallout as influenced by the nuclear explosions at the Nevada Proving Grounds during the early part of 1953. Data collected from approximately 50 air monitoring stations operated by the Regional Survey forces were used to determine the trend of radioactive particle concentrations in the atmosphere between March and June. These measurements were supplemented with the findings of associated organizations in the Biophysics Section during and immediately after the peak influx on May 26.
Date: August 4, 1953
Creator: Paas, H. J.; Adley, F. E.; ; ; Fuquay, J. J. & Jenne, D. E.
Partner: UNT Libraries Government Documents Department
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Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride

Description: The uranium recovery processes which are in operation or under construction at the present time--TBP, Redox and Purex--yield an aqueous uranyl nitrate solution as the recovered uranium product. For conversion of this recovered uranium to UF6 for feed to the gaseous diffusion plants, the uranyl nitrate in the solution is concentrated with or without prior organic stripping, calcined to UC3, reduced to UO2 with hydrogen, hydro-fluorinated to UF4 with RF, and finally fluorinated to UF6 with elemental fluorine.
Date: June 23, 1953
Creator: Clagett, F. & Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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Effect of Temperature on Uranium Recovery Columns Operation

Description: Some data on the temperature effect in pulse columns are reviewed. New data obtained with the "vibrational" stirrer are reported. The effects on both the dispersion and coalescence and the net rate of extraction suggest that improved operation of the RA column and lowered waste losses would be expected at elevated temperatures.
Date: August 12, 1953
Creator: Burger, L. L.
Partner: UNT Libraries Government Documents Department
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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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Backmixing in Pulse Columns II, Experimental Values and Effect of Several Variables

Description: Seven runs were made with the system Penn. Ref. Co. "Supersol" (dispersed) water (continuous) to investigate the effects of pulse frequency, amplitude plate spacing, volume flow ratio, and throughput on backmixing, using the technique of continuous injection of a tracer solution into the packed section. Backmixing was found to be surprisingly insensitive to all the above variables over the range studied with the exception of pulse amplitude and continuous phase flow rate, showing greatest dependence on the later. Backmixing increased with decreasing continuous phase flow rate and increased with pulse amplitude.
Date: August 11, 1953
Creator: Swift, W. H. (Ward Henry), d 1929- & Burger, L. L.
Partner: UNT Libraries Government Documents Department
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Monitoring Thermal and Resonance Neutron Flux

Description: The monitoring of thermal and resonance neutron flux in a thermal reactor having high flux over periods of time from 1 to 12 months using think Co foils is considered. Special attention is paid to the many correction factors to be applied to the activation data; neutron temperature, effective cadmium cutoff energy, burnout of Co59 and Co60, and decay of Co60. Results on a homogeneity test of 10 mil, 0.08% Co-A1 alloy foils is given.
Date: August 17, 1953
Creator: Heineman, R. E.
Partner: UNT Libraries Government Documents Department
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Surface Studies of Irradiated Graphite

Description: The effects of oxidation and irradiation on the microsurface structure of pile graphite have been investigated by measuring the surface area and pore size distribution of several samples. The results obtained for both oxidized and irradiated graphite samples indicate that changes in surface characteristics which occur are determined by the flux, temperature of irradiation, and gaseous atmosphere in which the radiation takes place.
Date: July 14, 1953
Creator: Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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Physical Properties of Tributylphosphate-Diluent Solutions

Description: In connection with the study of aqueous-tributyIphosphate (TBP) systems, the study of the interactions of various diluents with the TBP has been extended. The diluents used were mineral oil, Amsco 125-90W, dodecane, n-hexane, cyclohexane, benzene, n-octyl bromide, carbon tetrachloride, chloroform and pentachloroethane. The solubility of TBP in water from solutions of these diluents and the solubility of water in the organic phase was determined. For the paraffin hydrocarbons as diluents the solubility of TBP in water was found to increase with increasing molal volume of the diluent. No evidence for the formation of TBP-water complex of simple mole ration was found.
Date: September 1, 1953
Creator: Johnson, W. F. & Dillon, R. L.
Partner: UNT Libraries Government Documents Department
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Lattice Cell Calculations I: Determination of X for a Uranium Slug

Description: A first iteration of the diffusion theory result is executed for the thermal flux distribution in a 7.5" graphite-uranium lattice cell using the integral equation formulation of transport theory.
Date: August 24, 1953
Creator: Stuart, G. W., Jr.
Partner: UNT Libraries Government Documents Department
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Abrasive Cutting of Irradiated Uranium

Description: The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.
Date: September 17, 1953
Creator: Boyd, Carl L.
Partner: UNT Libraries Government Documents Department
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Use of Commercial Grade Methane in ASP Counting Instruments

Description: The gas commonly used in the chamber of the Simpson Proportional Alpha Counter (ASP) is the high grade, 99% pure methane. The cost of the gas has often raised the question of finding an adequate substitute and a number of substitutions have been attempted. Commercial methane has been substituted successfully for 99% pure methane and its use is recommended in ASP counters. Neither commercial nor technical methane caused any significant changes in instrument operation.
Date: October 8, 1953
Creator: Rasmussen, M. J.
Partner: UNT Libraries Government Documents Department
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