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Preliminary report on Bureau of Mines Yellow Creek corehole no. 1, Rio Blanco County, Colorado

Description: Analysis of geologic, hydrologic, and geophysical data obtained in and around Yellow Creek core hole No. 1, Rio Blanco County, Colorado, indicate a 1,615-foot section of oil shale was penetrated by the hole. Geophysical log data indicate the presence of 25 gallons per ton shale for a thickness of 500 feet may be marginal. The richest section of oil shale is indicated to be centered around a depth of 2,260 feet. Within the oil shale the interval 1,182 to 1,737 feet is indicated to be relatively structurally incompetent and probably permeable. Extension of available regional hydrologic data indicate the oil shale section is probably water bearing and may yield as much as 1,000 gallons per minute. Hydrologic testing in the hole is recommended.
Date: March 1967
Creator: Carroll, Roger D.; Coffin, D. L.; Ege, John R. & Welder, Frank A.
Partner: UNT Libraries Government Documents Department
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Doppler and related measurements in a soft fast-reactor spectrum

Description: This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
Date: March 24, 1969
Creator: Springer, T. H.; Tuttle, R. J.; Otter, J. M. & Pachall, R. K.
Partner: UNT Libraries Government Documents Department
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Crystalline Field Splittings in Holmium and Dysprosium Ethylsulfates

Description: From report : "It has become apparent that pragmatic resonance data alone are insufficient to correctly evaluate crystal field parameters for rare-earth ethylsulfates, and that heat capacity data above 20°K are a useful aid in determining whether low lying levels obtained by absorption spectroscopy have been correctly identified."
Date: March 1963
Creator: Spedding, F. H.; Gerstein, B. C.; Haas, W. J.; Phillips, E. & Sutherland, W. L.
Partner: UNT Libraries Government Documents Department
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Separation of Iron by Liquid-Liquid Column Extraction

Description: From abstract: "Iron(III) can be separated from many elements by extraction from 6 to ͟8M hydrochloric acid. The extraction is carried out by passing the aqueous hydrochloric acid solution through a column packed with 2-octanone adsorbed onto a poly-fluorocarbon resin. Fluoride, phosphate, sulfate or citrate cause no interference. Traces if iron(III) can be separated quantitatively from large amounts of copper(II) or zinc(II); traces of titanium(IV) can be separated from large amounts of iron(III)."
Date: March 21, 1962
Creator: Fritz, James S. (James Sherwood), 1924- & Hedrick, C. E.
Partner: UNT Libraries Government Documents Department
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The Mass Spectra of Some Volatile Hydrides

Description: From abstract: "The hydrides of group VB an VB elements, except CH4 and NH3, have been prepared and, except for PbH4 and BiH3, their mass spectra studied. Fragmentation patterns and appearance potentials of the positive ions from these hydrides are reported. The ions have been tested for excess kinetic energy and this energy was found to be negligible. The average M-H bond energies and the ΔHf° obtained from appearance potential data agree well with values obtained by other methods. Evidence is cited for the existence of distibine."
Date: March 19, 1962
Creator: Saalfeld, S. E. & Svec, Harry J. (Harry John), 1918-
Partner: UNT Libraries Government Documents Department
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Radical and Molecular Reaction Mechanisms for (γ, n) Activated c11 Reactions in Liquid Cyclohexane

Description: From abstract: "A study has been made of the yields of gaseous products labeled with C11 from the C12(γ, n) reaction in liquid cyclohexane. The effects of variations in the radiation dose and in the concentration of dissolved iodine during irradiation on the yields of these products were studied in order to elucidate the reaction mechanisms. A reaction model was developed as a method of assessing the relative importance of radical and molecular processes. The data suggest (1) that the formation of C11 labeled CH4, C2H4 + C2H6, and C3H6 involves a hot radical process while (2) the formation of C2H2 is by a molecular reaction with cyclohexane."
Date: March 21, 1962
Creator: Rack, Edward P. & Voigt, Adolf F.
Partner: UNT Libraries Government Documents Department
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αZ Correction to the Bethe-Maximon Pair Production Cross Section

Description: From abstract: "The first order correction in αZ to the Bethe-Maximon pair production cross section is calculated for the case where the incident photon and one of the electrons has an energy much greater than mc2. Comparison of these calculations to the experimental data of Plimpton and Hammer shows an improvement ina greement between theory and experiment of approximately a factor of 1+(αZ4π/15) for low positron kinetic energies. However, for positron kinetic energies of the order of 1 Mev no improvement is obtained."
Date: March 21, 1962
Creator: Moroi, David S. & Hammer, C. L.
Partner: UNT Libraries Government Documents Department
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͟v͟ic-Dioximes as Analytical Reagents

Description: This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.
Date: March 19, 1962
Creator: Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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Electrical Properties of the Tungsten Bronzes

Description: From abstract: "The electrical resistivity of NaxWO3, LixWO3, and KxWO3 has been measured at 300°K. The range of x-values was 0.25 < x < 0.9. All resistivities were characteristic of a metal and lie on a single curve. An extrapolation of the conductivity curve to zero conductivity indicated that the tungsten bronzes should be semiconductors for x < 0.25. The resistivities that have been measured for tungsten bronzes with x < 0.25 showed semiconducting behavior. The resistivity of LixWO3 exhibited an anomalous peak in the ρ vs Τ cuve. The Hall coefficient of Li0.37WO3 indicated one free electron per alkali atom as was previously found for NaxWO3. The Seebeck coefficient of NaxWO3 depended linearly on x[superscript]-2/3 as expected from free electron theory. The implications of these and some other data are discussed."
Date: March 21, 1962
Creator: Shanks, H. R.; Sidles, Paul Howard & Danielson, G. C.
Partner: UNT Libraries Government Documents Department
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Thorium-Molybdenum Phase Diagram

Description: From abstract: "The phase diagram of the thorium-molybdenum alloy system has been determined to be the eutectic type with a eutectoid reaction associated with the thorium alpha-beta transformation. X-ray, thermal, electrical resistance and metallographic methods have established the eutectic point at 1380 ± 10°C and 7.0 ± 0.5 wt % molybdenum. A eutectoid reaction is proposed at 1358 ± 5°C and less than 0.1 wt % molybdenum. No solubility of thorium in molybdenum was detected at 1325°C."
Date: March 27, 1962
Creator: McMasters, O. D.; Palmer, P. E. & Larsen, W. L.
Partner: UNT Libraries Government Documents Department
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Some Observations Regarding Rare-Earth Lactates

Description: From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcohol to a sirupy solution. Since it was not as deliquescent as the lactates of lanthanum, cerium, and praseodymium, some of its properties could be studied. The lactates of all the other rare earths, samarium through lutetium, as well as the lactate of yttrium, separated readily from aqueous media as trihydrates--the solubility of the hydrated lactate decreasing as the atomic number of the rare earth increased. Thermal decomposition of the crystalline lactates, except those of neodymium and samarium, proceeded through dihydrated and anhydrous states to a composition corresponding roughly to LnlacCO3 at a temperature of about 290-300°C. Ln2(CO3)3 or Ln2O(Co3)2 were observed. In order to make a comparison, thermal decomposition of the rare-earth glycolates was studied also. Solubilities in water at both 20 and 60°C have been tabulated."
Date: March 28, 1962
Creator: Powell, J. E. & Farrell, J. L.
Partner: UNT Libraries Government Documents Department
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Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Vessel Closure Stud Investigation

Description: Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grinding operation.
Date: March 23, 1962
Creator: Reali, D. L.
Partner: UNT Libraries Government Documents Department
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PM-2A Core II Zero Power Experiment

Description: Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of experimental data. Physical characteristics determined include distribution of fuel and B-10 in the fuel plates, minimum critical mass, control rod bank calibration, and integral rod worth. The report concludes with an analysis of the experimental data including estimated uniform and non-uniform burnup rates.
Date: March 30, 1962
Creator: Walthousen, L. D.; Mageean, J. V.; Raby, T. M. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
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Preliminary Technical Report SM-1 Core III with Type 3 Elements

Description: Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all conceivable special problems.
Date: March 30, 1962
Creator: Inglima, J. N.; Beam, R. H.; Davidson, S. L. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV

Description: Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
Date: March 30, 1961
Creator: Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
Partner: UNT Libraries Government Documents Department
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Suitability of Inconel for Corrosion Protection on Water Side of Sodium Component Steam Generator

Description: Abstract; The heat exchanger and steam generator for the U.S. Atomic Energy Commission Sodium Components Project will be constructed entirely of type 316 stainless steel. Because of the susceptibility of this alloy to stress corrosion cracking, it is proposed to clad all areas of the steam generator with Inconel where the stainless steel will be exposed to water and steam. This report includes a discussion of the work by numerous investigators that justify the selection of Inconel for this service. A discussion of Inconel type welding alloys is also included.
Date: March 1, 1961
Creator: Phillips, Laurence E. & Vawter, Frank J.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II With Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date: March 30, 1961
Creator: Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
Partner: UNT Libraries Government Documents Department
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Shielding Measurements at the SM-1 Reactor : June 1961

Description: Abstract: Neutron flux and gamma radiation measurements through the SM-1 primary shield were made at the startup of Core II in June 1961. They extend previous measurements (APAE-35) both vertically and horizontally in the primary shield and in the rod drive pit. Dose rate measurements on spent fuel elements under water are also reported.
Date: March 16, 1962
Creator: Moote, F. G. & Obrist, C. H.
Partner: UNT Libraries Government Documents Department
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A Transistorized Logarithmic Counter Ratemeter HASL Type TR-1

Description: Abstract: A four decade log count ratemeter based on a three diode pump section is described. The design equations for this system are included. The unit is contained in a chassis 3 1/2" high by 9 1/2" wide by 6" deep. All circuits are constructed on etched circuit boards to facilitate testing, construction, and servicing.
Date: March 1961
Creator: Graveson, R. T. (Robert T.)
Partner: UNT Libraries Government Documents Department
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Reactor Pressure Vessel Material Surveillance Program at the Garigliano Nuclear Power Plant

Description: Abstract: A materials exposure program has been established in the Garigliano Nuclear Power Plant to measure the effect of neutron irradiation and time at temperate on the mechanical properties of the reactor pressure vessel steel. Base metal specimens were made from portions of the pressure vessel steel, and weld heat-affected zone and weld metal samples were taken from a weldment made from the pressure vessel steel and simulating a pressure vessel circumferential weld since there are no longitudinal welds in the forged ring shell. The specimens were sealed in helium-filled capsules and placed in the reactor vessel at locations where they will be exposed to a variety of conditions. Tensile property changes will be measured by pre- and post-irradiation tests on small tensile specimens. Fracture characteristic changes will be measured in similar fashion by Charpy V-notch impact tests. The program is planned to cover a 32-year period, with specimens to be removed for test at intervals of 1, 2, 4, 8, 16, and 32 years.
Date: March 1964
Creator: Brandt, F. A. & Kobsa, I. R.
Partner: UNT Libraries Government Documents Department
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