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Radioactivity Dissemination Near Uranium Processing Mills

Description: This report follows a preliminary survey made to study radioactive contamination of the soil (and to some extent in the air and waters) in the vicinity of seven uranium processing mills.
Date: April 1, 1961
Creator: Feldman, M. H.; Troianello, Emilio J.; Coates, G. K. & Sheehan, W. R.
Partner: UNT Libraries Government Documents Department
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The Inference of Adsorption from Differential Double Layer Capacitance Measurements

Description: From Abstract : "Dependence of boundary tension and capacitance at the mercury-aqueous 0.1 N HClO4 interface on polarization and organic solute concentration were determined for the colutes n-amyl alcohol and phenol. ... An earlier treatment proposed by this Laboratory based on a (non-thermodynamic) assumption of linear variation of surface charge density with coverage appears adequately justified for inference of fractional surface coverages near the electrocapillary maximum, but must be considered approximate for evaluation of molar area at full coverage in cases where linear variation of charge with coverage has not been demonstrated."
Date: April 26, 1963
Creator: Hansen, Robert S.; Kelsh, Dennis J. & Grantham, D. H.
Partner: UNT Libraries Government Documents Department
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Removal of Radioisotopes From Solution by Earth Materials From Eastern Idaho

Description: Abstract: Naturally occurring earth materials from Idaho, primarily from localities near the National Reactor Testing Station (NRTS), were used in laboratory tests for the removal of radioisotopes from aqueous solutions. These earth materials included lignitic deposits, clay-like materials, and specific minerals; ion exchange resins were also considered for a specific application. The aqueous solutions were low-level radioactive cooling water or synthetic solutions made up to represent low-level radioactive wastes at the NRTS. Cation exchange capacities and other properties which affect the removal of radioisotopes from solution were determined the cation exchange capacities varied from 0.006 to 1.0 meq/g of solid. Earth materials with cation exchange capacities greater than 0.3 meq/g, in general, had distribution coefficients in excess of 1000. The highest distribution coefficients for cesium and strontium occurred in the pH range from 6.0 to 9.0 The possible use of these materials for decontaminating low-level radioactive waste at the NRTS is discussed. The result of laboratory studies using these materials and an organic ion exchange resign for decontaminating a specific NRTS waste are given. A material high in clinoptilolite from a location near the NRTS was considered to be the most promising material for use in large beds or ion exchange-type columns.
Date: April 1964
Creator: Wilding, M. W. & Rhodes, D. W. (Donald Walter), 1919-
Partner: UNT Libraries Government Documents Department
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gem-Bis(disubstitutedphosphinyl)alkanes. II. Extraction Properties of Bis(di-n-hexlphosphinyl)methane

Description: From abstract: "Bis(di-n-hexylphosphinyl)methane, HDPM, [(C6H13)2P(O)]2CH2, has been studied as an extractant for a variety of metals. HDPM was evaluated as an extractant for uranium(VI) and compared with tri-n-octylphosphine oxide, TOPO, (C8H13)3PO. In nonpolar solvents, HDPM forms a polymeric-like substance with compounds of uranium(VI). Viscosity measurements indicate that the molecular weight of this polymeric-like substance is about 100 times greater than the corresponding complex with TOPO. Polymer formation occurs only when nonpolar solvents are used as diluents for HDPM and is easily avoided by using polar solvents such as 1,2-aichlorobenzene. HDPM forms 1:1 and 2:1 complexes with uranium(VI) nitrate. Equilibrium constants for these complexes as well as that for the 2:1 TOPO complex were calculated and it was shown that the over-all constant is at least ten times larger for the HDPM complex than for the TOPO complex. The effect of concentration of various mineral acids, extractant concentration, temperature, and diluents on the extraction of uranium are discussed."
Date: April 11, 1961
Creator: Burke, Keith E.; Sakurai, Hiroshi; O'Laughlin, Jerome W. & Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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High Purity Calcium

Description: Technical report. From Introduction : "For more than a century, methods employed in preparing calcium were based largely on electrowinning and the most successful were based on [Sir Humphrey] Davy's process. ... In general, the metal was of adequate quality for the industrial applications of the time, and although by 1940 some strides had been made in the purification of calcium, interests in the better grades of the metal were limited essentially to experimental work of academic concern."
Date: April 3, 1963
Creator: Wilhelm, H. A. & Carlson, O. N.
Partner: UNT Libraries Government Documents Department
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Design and Test of a Diaphragm Pump for Liquid Metals

Description: Technical report. From Abstract : "Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of 5,376 hr. test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated and also where remote operation is required. Operating temperatures and pressures are limited only by the availability of suitable materials of construction."
Date: April 12, 1963
Creator: Westerheide, D. E. & Clifford, J. C.
Partner: UNT Libraries Government Documents Department
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Measurement of Thermal Properties by the Arc Image Furnace

Description: Technical report. From Abstract : "A number of imaging furnace systems and sources are discussed with emphasis on the carbon arc image furnace. Several potential applications of the carbon arc image furnace in high temperature research are described and a new method of heat capacity determination is discussed."
Date: April 16, 1963
Creator: McMahon, W. R. & Wilder, D. R.
Partner: UNT Libraries Government Documents Department
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The Mass Spectra of the α-Amino Acids

Description: From abstract: "The mass spectra of the α-amino acids have been obtained in a mass spectrometer equipped with a heated crucible ion source. Correlations of these data have been made with the molecular formulae of the ion fragments, and mechanisms leading to these fragments are proposed. Comparisons of these data have been made with the mass spectra of the ethyl esters of the amino acids and with other carboxylic acids and their esters."
Date: April 9, 1962
Creator: Junk, Gregor & Svec, Harry J. (Harry John), 1918-
Partner: UNT Libraries Government Documents Department
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Formation Constants of the Complex Species Formed by Interaction of Rare-Earth Nitrilotriacetate Complexes with an Equivalent Amount of Base

Description: From abstract: "The formation constants of the RChOH- species, formed by interaction of individual rare-earth nitrilotriacetate species and KOH at 25°C and an ionic strength of 0.1, have been determined by the potentiometric method, i.e., computed from the pH values of equilibrium mixtures containing varying proportions of rare-earth complex and base. The relationship of these constants to the ion-exchange separation of rare earths at high pH has been discussed."
Date: April 13, 1962
Creator: Guptak, Asim K. & Powell, Jack E.
Partner: UNT Libraries Government Documents Department
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Progress in Sintering

Description: From abstract: "Sintering is broadly defined as all aspects of the adhesion, densification, shrinkage, and consolidation which accompanies the reduction in surface energy of a powder compact which occurs upon application of heat and/or pressure. The process of sintering is then further divided into the initiation, material transport, and grain growth-recrystallization stages. A general review is made of each of these stages, noting typical work which has contributed to progress in each area involved."
Date: April 16, 1962
Creator: Wilder, D. R.
Partner: UNT Libraries Government Documents Department
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The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
Partner: UNT Libraries Government Documents Department
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Simple High-Voltage Trapezoidal Pulse Generator

Description: From abstract: "A description is given of a simple circuit used to produce negative voltage pulses up to 60 kilovolts with a portion rising with constant slope up to 10 kilovolts per microsecond."
Date: April 2, 1962
Creator: Gonella, Luigi
Partner: UNT Libraries Government Documents Department
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The Application of Wax Laps to Vibratory Polishers

Description: From introduction: "In this paper the adaptation of the wax lab surface vibratory polisher is described. The wax lap requires little maintenance during the life of the lap. It is not necessary to remove any of the holding devices on the bowl to clean and recondition the lap. The bowl is merely washed out, recharged and placed in operation. The wax lap will not wrinkle or tear, nor is it necessary to change it each day such as the silk or nylon cloths."
Date: April 19, 1962
Creator: Hopkins, E. N. & Peterson, D. T.
Partner: UNT Libraries Government Documents Department
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DuPont Prototype Safety and Control Rod Drive Testing

Description: Summary: Prototype testing of the safety and control rod drives indicated that both units functioned properly. No major problems were encountered during testing. Seal leakage data collected indicated that the seal units were performing satisfactorily. Scram times during both cold and hot testing were excellent and actually better than expected.
Date: April 25, 1960
Creator: VandeMark, G. M. & Krause, P. S.
Partner: UNT Libraries Government Documents Department
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A Survey of the Effects of Neutron Irradiation on the Impact and Other Mechanical Properties of Pressure Vessel Steels for the SM-2 Reactor

Description: Abstract: This technical report summarizes the data obtained in a recent literature survey conducted to determine the effects of neutron irradiation on the impact and other mechanical properties of both ferritic steels and austenitic stainless steels. The survey was primarily aimed at obtaining sufficient data on the behavior of pressure vessel steels at high integrated neutron flux levels in order that a reference material of construction could be selected for the SM-2 (APPR-1B) reactor vessel. Materials studied in this literature survey included carbon and low alloy steels such as: ASTM A-212B, ASTM A-201, ASTM A-301B (CR-Mo), ASTM A-106 (coarse and fine grained), ASTM A-285, ASTM A-302B (Mn-Mo), ASTM A-353, ASTM A-203 Grade D, E-7016 carbon steel weld metal, USS Carilloy T-1, HY-65 and HY-80. In addition, Types 304 and 347 stainless steels were also investigated as representative austenitic materials which might be used in pressure vessel construction. A careful evaluation was made of the irradiation induced changes in the mechanical properties of the above materials. The ferritic steels were evaluated primarily on the basis of increases in transition temperature due to irradiation and decreases in the amount of maximum energy absorbed prior to ductile failure. Factors such as industrial experience, changes in other mechanical properties and the susceptibility of these materials to temper embrittlement were also considered. Austenitic stainless steels were evaluated on the basis of post-irradiation and low temperature impact strength and on irradiation induced changes in other mechanical properties. Based on available data, it is concluded that austenitic stainless steels are capable of resisting harmful property damage at integrated neutron fluxes > 1 Mev of at least t to 2 x 10(21) nvt. However, with the application of special reactor operating procedures, ASTM A212B will be satisfactory at integrated neutron fluxes up to 5 x 10(19) nvt.
Date: April 1, 1960
Creator: Kelleman, Richard William.
Partner: UNT Libraries Government Documents Department
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Coextrusion of Powder-Compact Slugs

Description: Technical report. From Abstract: "A process was developed for manufacturing aluminum-clad slugs containing UO2 or ThO2 dispersed in an aluminum matrix. In this process a mixture of the oxide and aluminum powder is cold compacted to form the billet core, which is then coextruded with an aluminum sheath to produce the clad slug."
Date: April 1960
Creator: Marsh, Harold G.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of Aluminum-Lithium Alloys Containing Up to 8% Lithium

Description: Technical report. From Abstract: "The thermal conductivities of aluminum-lithium alloys containing up to * wt % lithium were determined at temperatures between 125 and 260ºC. The addition of lithium to aluminum sharply reduces the conductivity from 0.60 cal/(sec)(ºC)(cm) for pure aluminum to 0.22 cal/(sec)(ºC)(cm) for 2 wt % alloys; further addition linearly and more gradually decreases the conductivity to 0.16 cal/(sec)(ºC)(cm) for a 7.9 wt % alloy."
Date: April 1960
Creator: Costas, Louis P.
Partner: UNT Libraries Government Documents Department
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Automatic Dose Computer for Radiation Film Badges

Description: Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."
Date: April 1960
Creator: Davis, John E.
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
Partner: UNT Libraries Government Documents Department
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Fabrication of fuel Cladding From Incoloy Alloy 800 : an Evaluation of Methods

Description: Summary: On the basis of its high temperature, physical and corrosion properties, Incoloy Alloy 800 was selected as a candidate for fuel cladding nuclear superheat applications. At the time of its selection, there was little information or experience with Incoloy 800 in the production of thin-walled, small diameter tubing suitable for nuclear fuel cladding. As a result, special purchasing efforts were required for the procurement of initial tubing used in fuel fabrication. As-received welded and drawn tubing proved to be generally good but showed some conditions which were undesirable, the major one being lack of complete recrystallization and homogenization of the weld zone. The possible effect of this condition upon the fuel performance was not immediately known; however, subsequent development work indicated that the non-homogeneity of the weld could affect adversely its mechanical and corrosion properties in relation to the parent metal. A development program was initiated to determine treatment sequences suitable for the fabrication of welded and drawn tubing with a fully recrystallized and homogenized weld structure. This was accomplished by butt welding lengths of Incoloy strip which were subsequently cold rolled and annealed to simulate tube fabrication steps. Requirements imposed on this work were that all processes developed must be amenable to normal production equipment and procedures used in commercial tube manufacturing. As a result of the experiments undertaken, a sequence of cold drawing and annealing steps was established suitable for recrystallization and homogenization of weld zones in welded-and-drawn tubing. In order to obtain complete sequential chemical and metallurgical history of nuclear grade Incoloy 800 tubing, a 3000-pound ingot was purchased to the required chemical specifications and reduced to tubing through both seamless and welded drawn routes. The management of the sequential metallurgical steps needed for tubing fabrication resulted in establishing a workable process through a series of …
Date: April 1964
Creator: Kirby, R. F.; MacMillan, D. F. & Punches, J. R.
Partner: UNT Libraries Government Documents Department
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The Effects of Non-Uniform Flow and Concentration Distributions and the Effect of the Local Relative Velocity on the Average Volumetric Concentration in Two-Phase Flow

Description: Abstract: A general expression which can be used either for predicting the average volumetric concentration or for analyzing and interpreting experimental data is derived. The analysis takes into account both the effect of non-uniform flow and concentration profiles as well as the effect of the local relative velocity between phases. The first effect is taken into account by a distribution parameter, whereas the latter is accounted for by the weighted average drift velocity.
Date: April 1964
Creator: Zuber, N. & Findlay, J. A.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Tenth Quarterly Report, January-March 1964

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, transient testing of fuel, fuel performance evaluation, fast-flux irradiation of fuel, and reactor physics and core analysis.
Date: April 1964
Creator: Breizy, C. E.
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1964

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Work has begun in the Radioactive Materials Laboratory to sample the project fuel from the pins irradiated to 1800 and 5000 MWT/T. Some delay has been experienced due to preemption of the hot cells by priority work. Examination of the autoradiographs of the un-irradiated project fuel showed that in a volume of fuel approximately equivalent to a pellet there were 13 hot spots larger than 15 mils. Evaluation of these spots with the fuel analyzer showed that they contained about 14 mg of PuO2 or about 9% of the total present. The EPITHERMOS code is being modified to automatically normalize the epithermal scattering to the correct value for all moderators. Calibration of the flux wires has been made and the reduction of the data from the VBWR irradiation is nearly complete. A similar resonance activation was made in the water reflector of the Stanford Pool Reactor to obtain the relative activity in a well-defined pure water spectrum. Reduction of these data is also in progress.
Date: April 15, 1964
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

Description: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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