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A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations

Description: An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date: April 1963
Creator: Walker, D. G.
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A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method

Description: An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date: April 1963
Creator: Walker, D. G.
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ARMY REACTORS PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING OCTOBER 31, 1962

Description: ; 8 7 < 8 < : : : 6 9 9 = < 9 < : 5 < > ;" icipation in the program continued to include review, inspection, and support in various areas of reactor technology. An advanced fuel irradiation test program was established that is to be conducted in the pressurized-water loop in the Oak Ridge Research Reactor. Review of the design of the MH-1A reactor was initiated. This reactor, a pressurized-water system fueled with low- enrichment bulk UO/sub 2/ clad with stainless steel, is being designed as a … more
Date: April 10, 1963
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Borax V Exponential Experiment

Description: The cadmium ratio was measured in an exponential mockup of Borax V as a function of the void fraction. The extent of voids, simulated by lengths of closed polyethylene tubes, ranged from 0 to 40%. The corresponding cadmium ratios ranged from 6.1 to 4.6. The exponential was also used to determine the radial flux pattern across a Borax-type fuel assembly and the fine flux detail in and around fuel rods. For a normal loading the maximum-to-average power generation across an assembly was 1.24. (aut… more
Date: April 1963
Creator: Kirn, F. S. & Hagen, J. I.
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C reactor overbore fuel examination

Description: On April 16, 1962, the fuel charge in overbore tube 3062-C sustained a failure, and upon examination after discharge was found to contain three split failures and three ``worm tracked`` elements (depression in the aluminum cladding apparently the result of uranium cleavage and subsequent yielding of the cladding). These failures occurred approximately ten days following a period of reactor neutron flux cycling, and during a second cycle at C Reactor. In addition to the failures, a total of 17 e… more
Date: April 18, 1963
Creator: Hladek, K. L.; Teats, R. & Weakley, E. A.
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Characteristics of Fuel Compounds and Encapsulation Materials in Radioisotope Heat Sources

Description: The properties of radioisotope fuel compounds and fuel capsule materials which are pertinent to the design and operation of radioisotope heat sources are outlined. These properties are grouped into the following categories: intrinsic, extrinsic, and compatibility. The properties of strontium titanate as the fuel and Hastelloy C as the capsule material are evaluated. (D.L.C.)
Date: April 17, 1963
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Chemical Processing Department Monthly Report: March 1963

Description: This report, from the Chemical Processing Department at HAPO for March 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.
Date: April 22, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
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CORE TRANSFER FUNCTION MODELS FOR SNAP SYSTEM KINETICS

Description: A distributed parameter transfer function is developed for SNAP type reactor cores. The coolant may be either boiling, non-boiling, or both. In the boiling case the Bankoff model is used to find the spatial distribution of voids. The transfer functions obtained are not simple polynomials. However, they are readily analyzed for stabilily using the 7090 program TRAFIC, which uses a Nyquist diagram approach. Some general conclusions resulting from these calculations are included. (auth)
Date: April 29, 1963
Creator: Johnson, R. L.
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Correlation of Liquid Fraction in Two-Phase Flow With Application to Liquid Metals

Description: A generalized correlation for the liquid fraction in twophase flow is presented which is proposed for use with all iluids, including liquid metals. The correlation is based on isothermal, two-phase, two-component liquid fraction data for liquid Hg--N/sub 2/ and water-air. Liquid fraction is shown to be a function of the Martinelli flow modulus and liquid/gas density and viscosity ratios. Good correspondence is indicated between the liquid fraction predicted by this correlation and the Martinell… more
Date: April 15, 1963
Creator: Baroczy, C. J.
open access

Critical Studies of a Small Uranium Carbide-Fueled Reactor With a Beryllium Reflector. (ZPR-III Assembly 40)

Description: A small, lightweight, uranium carbide-fueled reactor with a beryllium reflector surrounding the core was mocked up as Assembly 40. It was determined that the presence of beryllium in the axial and radial reflectors did not endanger the safe loading and operation of the' critical assembly. The actual experiment consisted of determination of the critical mass, measurement of the reactivity coefficients for a large number of fissile and nonfissile materials, the performance of radial and axial fis… more
Date: April 1, 1963
Creator: McVean, R. L.; Amundson, P. I.; Brunson, G. S. & Gasidlo, J. M.
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A Cryostat for Temperature Control in the Range from Ambient to - 150 degrees C

Description: This note describes a simple cryostatic device, which, by utilizing the latent heat of vaporization of liquid nitrogen, enables accurate control of temperature between ambient and - 150 degrees C. The advantages of this cryostat over other models known are simplicity of design and operation, ability to operate accurately from ambient to - 150 degrees C, economy, and large working space.
Date: April 1963
Creator: Roman, D.
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Cumulative Bibliography of Literature Examine by the Radiation Shielding Information Center

Description: This bibliography represents the first cumulative edit of the literature examined by the Radiation Shielding Information Center recently established at the Oak Ridge National Laboratory. Its two major sections consist of a list of documents by subject category and of an author index. The document list covers nine major subjects with a total of 118 categories; however, literature specimens have not yet been entered for all categories. If a document applies to more than one category, it is listed… more
Date: April 1963
Creator: Radiation Shielding Information Center (U.S.)
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Data for Elementary-Particle Physics

Description: These data are provided: Masses and .Mean Lives of Elementary Particles; Atomic and Nuclear Properties of Materials; Particle Scattering; Atomic and Nuclear Constants; Particle Decay and Reaction Dynamics; Tentative Data on Strongly lnteracting Particles and Resonances; and Clebsch-Gordan Coefficients and Spherical Harmonics.
Date: April 30, 1963
Creator: Rosenfeld, A. H. & Barkas, W. H.
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DENITRATION OF PUREX WASTES WITH SUGAR

Description: A process was developed for the destruction of HNO/sub 3/ in Purex-type waste solutions using sugar. Polyhydroxy compounds such as sucrose, fructose, glucose, and crude syrups such as black strap molasses rapidly and controllably decompose HNO/sub 3/ in aqueous solutions at temperatures above approximately 85 deg C. The number of moles of HNO/sub 3/ destroyed per mole of sugar fed is a function of the temperature of reaction and the moles of dissolved multivalent metal cations (such as iron and… more
Date: April 1, 1963
Creator: Bray, L. A.
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Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: The Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR- II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyrometallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5% fissium and contains about 46 wt.% U/sup 235/ . The blanket material consists of U in which plutonium is bred. Core and blanket subassemblies contained in tr… more
Date: April 1, 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
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Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and bla… more
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
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