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Nuclear Thermodynamics of the Heaviest Elements. II

Description: The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and so… more
Date: January 1, 1958
Creator: Foreman Jr., Bruce M. & Seaborg, Glenn T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle in the Calder Hall Type Reactor

Description: The economiics and physics of four schemes of pIutonium recycle in the Calder Hall type reactor are considered. The four possible schemes are: (I) to blend the Pu produced In a run with fresh naturaI U for a subsequeut run; (2) to alloy the Pu with somie diIuent metal and fabricate the alloy Into high heat- transfer elements morc like MIR or PWR-sced type elements and"spike' a subsequent load of fresh natural U elemients with these Pu elemicnts; (3) to recycle half the spent U as well as the Pu… more
Date: January 1, 1958
Creator: Barbieri, L. J.; Webster, J. W. & Chow, K. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Power Transfer Functions of the EBWR Obtained Using a Sinusoidal Reactivity Driving Function

Description: A series of reactor frequency response measurements, relating flux or power level to a reactivity input function, were made to evaluate reactor stability for different values of power parameters. These parameters included: power level, steam pressure, and control rod position. The results were extrapolated to predict EBWR stability at higher operating powers. The experimental data may also be used to evaluate the thermodynamic and hydraulic constants. (authl
Date: January 1, 1958
Creator: DeShong, J.A. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature and Phase Effects on the Photolysis of Ethyl Iodide

Description: The elementary sieps in the photolysis of liquid ethyl iodide by light of wavelength 2537 A by determining initial rates of iodine production in the presence.of added iodine and hydrogen iodide were analyzed at 25 and --70 d C to get information on the activation energies of competing elementary reaciions. Investigations were also made of the effects of additives on the photolysis of glassy ethyl iodide at --180 d C, and evidence for the formation of trapped radicals during photolysis and radio… more
Date: January 1, 1958
Creator: Luebbe, R.H. Jr. & Willard, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Irradiation of Some Uranium-Plutonium Alloys. Final Report-- Metallurgy Program 6.5.3 Work Completed: March 1955

Description: Irradiations were made on a number of uranium-plutonium alloy specimens made from both cast and extruded materials. The cast alloys included alloys of uranium with 3.7, 5.6, and 13.0 wt. % plutonium, and the extruded alloys included alloys of uranium with 9.5, 14.1, and 15.7 wt.% plutonium. One-half of the extruded specimens were given a heat treatment consisting of heating to 545 deg C and cooling to and holding at 500 deg C for one hour in an attempt to remove the preferred orientation that w… more
Date: January 1, 1958
Creator: Kittel, J. H. & Kelman, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OPTIMIZATION OF FISSION FRAGMENT CATCHER FOIL EXPOSURE TIME

Description: The exposure-time for fission fragment catcher foils, used in nuclear reactor power mapping, was arbitrarily set at 20 minutes. Work performed to evaluate this choice and to attempt an optimization of the exposure time is reported. A true optimum was not found. Forty minute runs are suggested, however, as a practical optimization and as an alternative to the 20 minute runs in current usage. (auth)
Date: January 1, 1958
Creator: Renaker, J.N. & Clark, R.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DOSIMETRY IN THE ARGONNE HIGH-LEVEL GAMMA-IRRADIATION FACILITY

Description: The oxidation of ferrous sulfate is used as the method of measurement of radiation intensity in the Argonne National Laboratory's High-Level-Gamma Food Irradiation Facility. The preparation and calibration of the dosimeters are described and illustrated photcgraphically. (C.H.)
Date: January 1, 1958
Creator: Swope, H.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE SODIUM-COOLED, D$sub 2$O-MODERATED REACTOR (SDR). Status Report

Description: For presentation at the 1958 Nuclear Congress, Nuclear Science and Engineering Conference, March 17The experimental program was focused on the problems of containing the Na, of providing a barrier material with low neutron absorption cross section and an ability to withstand the action of hot Na, of developing an arrangement of this material which is mechanically adequate, and of demonstrating that an integrated barrier system can be safety operated under reactor tempernture and pressure condit… more
Date: January 1, 1958
Creator: Goldmann, K. & Leeper, C.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REMOTE MAINTENANCE TOOLS CATALOG NO. 58

Description: Catalog number 58, containing information concerning remote maintenance tools which have been used at ORNL, is presented. It is intended as a guide and as a starting point for modification work. Complete information is not available on all tools. (J.R.D.)
Date: January 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE FABRICATION OF FUEL SUBASSEMBLIES FOR THE BORAX-III REACTOR

Description: Each Borax-lIl fuel subassembly consists of a group of aluminum-clad aluminum-uranium alloy fuel plates arranged in an MTR-type array. The fuel plates are electric-resistance spot-welded to two aluminum sideplates and an aluminum central-support plate. An anuminum-0.6 wt.% boron, burnable poison strip is attached to each fuel subassembly. The poison strips are made by hot extruding a mixture of aluminum and elemental boron powders in the desired proportions. (auth)
Date: January 1, 1958
Creator: Walker, D.E. & Noland, R.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry of Uranium. Collected Papers

Description: Originally intended for publication as NNES-VIII-7. Elghty-one papers are presented on thc chemistry of uranium. (W.L.H.) 13236(Abstract unscannable)
Date: January 1, 1958
Creator: Katz, J.J. & Rabinowitch, E. eds.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTOR PHYSICS CONSTANTS

Description: This compilation of reactor physics constants, based on data available up to March 15, 1958, is the first publication of the Reactor Physics Constants Center (RPCC). The primary objective of the RPCC is the periodic compilation of the latest and best values of the constants, recipes, formulas, etc., which are necessary to calculate reactor characteristics. (W. D.M.)
Date: January 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pretreatment of Fuel Elements. Technical Report No. 48 Chapter 130

Description: A revitew is presented of pretreatment methods with special attention to those useful at Eurochemic. Mechanical and chemitcal decanning methods presently in use or proposed for Al-, Mg-, stainiless steel-, and Zror Zr alloy-jacketed fuels are discussed. Darex, Sulfex, and Zirflex processes are included along with special methods ror U-- Mo and U- Zr fuels. (T.R.H.)
Date: January 1, 1958
Creator: Detilleux, E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress-Strain Properties of Irradiated Uranium-10 w/o Molybdenum

Description: The stress-strain properties of the APDA reference alloy of uranium- 10 wt.% molybdenum at various burnups up to 2.1 total at. % are described. Data were ob tained on both irradiated and unirradiated specimens of the alloy by the use of a remotely operated bend-testing machine. Tensile properties of unirradiated material are also reported for comparison with data obtained from the bend tests. The mathematical procedure used in obtainirg equivalent uniaxial stress-strain properties from the bend… more
Date: January 1, 1958
Creator: Gates, John E.; Bodine, Edward G.; Bell, J. Clarence; Bauer, Arthur A. & Calkins, George D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PARTICLE ACCELERATORS. PART I. BIBLIOGRAPHY. PART II. LIST OF ACCELERATOR INSTALLATIONS

Description: References to accelerators and accelerator technology in the technical literature from July 1954 through June 1957 are listed in Section 1, the bibliography. Most of the references are taken from Nuclear Science Abstracts, Chemical Abstracts, Physics Abstracts, and Electrical Engineering Abstracts. In Section H, accelerator installations throughout the world are listed together with the types of particles accelerated and the energy and other characteristics of the machines. (auth)
Date: January 1, 1958
Creator: Behman, G.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HYDROGEN REDISTRIBUTION IN THIN PLATES OF ZIRCONIUM UNDER LARGE THERMAL GRADIENTS

Description: By using experimental data, the quantities determimng the extent of dissolved H redistribution under a thermal gradient in Zircaloy were calculated. It is concluded that the phenomenon of hydride precipitation by means of thermaI gradient diffusion of dissolved H in Zircaloy fuel plates and cladding places much more severe restrictions on the allowable pre-operation H content of such elements than was hitherto suspected. The specific effects of operating conditions on H content of plates and cl… more
Date: January 1, 1958
Creator: Markowitz, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Remarks on the Stability of Boiling Heat Transfer. Report 58-5

Description: An analytical expression is presented which permits the prediction of the maximum nucleate heat flux in pool boiling of saturated or subcooled liquids. The numerical values of the empirical constants which appear in the Kutateladze and Borishanskii criteria for the burnout'' heat flux are derived from the theory. An analytical expression for the empirical function which appears in the correlation of Griffith is also derived. The hitherto unexplored features of transition boiling, i.e., the hydr… more
Date: January 1, 1958
Creator: Zuber, N. & Tribus, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Continuous Uranium Monitoring of a Liquid Metal Fuel Reactor. Report to Babcock and Wilcox Co. Atomic Energy Div'

Description: Many types of measurement systems were reviewed for appropriateness of the task of continuous uranium monitoring of a liquid-metal fuel reactor. Of these, the three general classes of neutron methods, x-ray methodss and paramagnetic suseeptibility methods were selected for detailed evaluations primarily for the case of liquid-fuel stream monitoring. In additions the present state of development of electrochemical and spectroscopic methods for application to fused-salt monitoring was assessed. T… more
Date: January 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Environmental Radioactivity at Argonne National Laboratory. Report for the Year 1956

Description: Concentrations of radioactivity in several types of samples obtained from the ANL site and from locations approximately 10, 25, and 100 miles from the Laboratory are given. Since ANL waste water is discharged into Sawmill Creek, which in turn empties into the Des Plaines River, special emphasis was placed on sampling these streams. Most of the results were obtained by coumting the total alpha and beta activities after suitable preparation of the samples. Some of the samples were also analyzed f… more
Date: January 1, 1958
Creator: Sedlet, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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