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Storm Data and Unusual Weather Phenomena, Volume 2, Number 2, February 1960

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: March 30, 1960
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Selected Alloys at Elevated Temperatures, Part 2: Design Criteria of Silicon Carbide

Description: Report describing a research study to determine in broad parameters the areas where a brittle, non-metallic body such as silicon carbide might be used in aircraft construction and establishing methods for obtaining these properties. A theoretical and literature review, design parameters, discussion of the testing phase, and test specimen geometry explanation are included.
Date: March 1960
Creator: Pearl, Harry A.; Nowak, John M. & Deban, Harry G.
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Selected Alloys at Elevated Temperatures [Part 1]

Description: Report describing a research study to provide material property data of the type and quality necessary for efficient design of hot aircraft and missile structural components. Six materials in plate and bar form were subjected to tension, compression, bearing, and shear stresses at various temperatures. Preliminary considerations of the study, testing apparatus, calibration and accuracy of the equipment, testing procedures and results are discussed.
Date: March 1960
Creator: Pearl, Harry A.; Kappelt, George F. & King, Edmund J.
Partner: UNT Libraries Government Documents Department
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Power Reactor Development Company Monthly Report: March 1960

Description: Monthly report describing activities and progress related to research and development at the Power Reactor Development Company.
Date: March 1960
Creator: Power Reactor Development Company
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Progress Report for October Through December, 1959

Description: The status of the Eurochemic (European Company for the Chemical Processing of Irradiated Fuels) Organization and the preliminary plant design are summarized. This report covers the progress during the period October through December 1959, gives the status of the program as of January 1, 1960, and outlines the anticipated assistance from the United States for the next 6 months.
Date: March 31, 1960
Creator: Nicholson, E. L. & Shank, E. M.
Partner: UNT Libraries Government Documents Department
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Numerical Three Dimensional Temperature Analysis Of The EGCR Fuel Rod

Description: The temperature field in an outer rod of the EGCR fuel assembly is presented. The numerical analysis has taken account of the three dimensional spatial dependence of the thermal neutron flux and has considered the four regions involved, that is, fuel pellets, ceramic disc, steel end caps, and cladding. The convective heat transfer coefficient and fluid temperature were considered constant over the 2.185 in. of rod length studied.
Date: March 21, 1960
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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HRT-Chemical Plant Runs 18 And 19 Summary

Description: The HRT chemical plant was operated for 1070 hours during reactor runs 18 and 19, removing solids from a new feed point, in the reactor core near the junction of the top diffuser screen and the core wall. Corrosion product solids data removal data for those runs is summarized here, with data from runs 16 and 17 included for comparison.
Date: March 25, 1960
Creator: Yarbro, O. O.
Partner: UNT Libraries Government Documents Department
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Development Testing And Performance Evaluation Of Liquid Metal And Molten Salt Heat Exchangers

Description: This memo contains two companion papers presented at the 1959 winter meeting of the American Nuclear Society in Washington, D.C. The papers cover work performed on development testing and performance evaluation of liquid metal and molten salt heat exchangers in support of the Aircraft Nuclear Propulsion program at the Oak Ridge National Laboratory.
Date: March 17, 1960
Creator: MacPherson, R. E.; Yarosh, Marvin M.; Amos, J. C. & Savage, H. Wesley
Partner: UNT Libraries Government Documents Department
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Interim Report To Oak Ridge National Laboratory Relating To A Digital Data Acquisition System For Use With The Homogeneous Reactor Test Facility

Description: This interim report presents the findings of a survey of the HRE-II. Its purposes are to define the useful functions which could be performed by an on-line computer system, the describe in detail the equipment which would be required, and to present figures for determining the cost of installing a computer system.
Date: March 29, 1960
Creator: Adams, R. K.; Burger, G. E.; Pfretzschner, C. A. & Schy, S. T.
Partner: UNT Libraries Government Documents Department
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Rare Earth Chromatography Using Bis(2-ethylhexyl) Orthophosphoric Acid

Description: Several techniques of column construction have been tested for the chromatographic separation of the rare earths using bis(2-ethylhexyl) orthophosphoric acid (HDEHP). Earlier work, which showed that rare earth separations can be made by HDEHP supported on an aluminum oxide column and elution with hydrochloric acid, has been continued in order to develop a procedure for rare earth chromatography in connection with neutron activation analysis. Three column techniques show promise, according to in… more
Date: March 14, 1960
Creator: Winchester, John W.
Partner: UNT Libraries Government Documents Department
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Comment On Calculations By Lietzke And Stoughton On Concentrations Of Species In Aqueous UO2SO4 Solutions As A Function Of Temperature

Description: Using the same techniques as Lietzke and Stoughton, the solubility of silver sulfate in uranyl sulfate solutions was measured and analyzed. A general IBM-704 computer code was written which could calculate the concentration of all the species assumed to be present in the solutions.
Date: March 31, 1960
Creator: Greeley, R. S.
Partner: UNT Libraries Government Documents Department
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Polfit, A 704 Program For Polynomial Least Squares Fitting

Description: A polynomial least squares fitting subroutine has been written for the IBM-704 computer. This subroutine may be used in any Fortran II program where a least squares fit is desired. A calling program has been written to do a polynomial least squares fit, error analysis, and give solutions of the resulting equations for any desired values of the independent variable.
Date: March 30, 1960
Creator: Lietzke, M. H. & Lietzke, Marjorie P.
Partner: UNT Libraries Government Documents Department
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The Applicability of Packed Glass Raschig Rings For Nuclear Safety In Large Vessels

Description: Simple calculations indicate that large diameter vessels packed with boron-containing glass raschig rings are applicable for storage of high concentration solutions of fissile material. Use of this means for storage of fissile solutions can result in appreciable savings. Advantages and disadvantages are discussed and tests are enumerated that must be made to confirm the applicability of glass raschig rings as a fixed poison.
Date: March 24, 1960
Creator: Nichols, J. P.
Partner: UNT Libraries Government Documents Department
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Apparent Copper Rate Constants Determined In In-Pile Loop Experiment L-2-22

Description: The results of radiolytic gas pressure measurements in the pressurizer of in-pile loop experiment L-2-22 were used to calculate the copper rate constants in the several different test solutions. Values for the copper concentration obtained from solution analyses were combined with the solution rate constants to determine the apparent molar rate constant for each solution at 280'C.
Date: March 23, 1960
Creator: Jenks, G. H. (Glenn Herbert), 1916- & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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Some Remarks On The Contribution Of Fission-Product Cesium To The Pressure Buildup In UO2 Fuel Elements

Description: The large fission yield of cesium and its apparent mobility in hot UO2 cause concern that it may contribute importantly to the pressure buildup inside clad fuel elements. A study has indicated that the pressure will essentially be that of metallic cesium and no significant addition will result from the formation of chemical compounds.The vapor pressure in a fuel element will be that associated with the coldest point accessible to the vapor.
Date: March 18, 1960
Creator: Rosenthal, M. W. & Cantor, S.
Partner: UNT Libraries Government Documents Department
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Study Of Outage Experience With Selected Boiler And Turbine Generator Units

Description: Because of consideration that is being given to the feasibility of building small nuclear power plants to operate for one to three years with no attention or maintenance it was decided to appraise the degree of reliability that might be anticipated in conventional systems. A preliminary study was made of outages in both common header turbine generator and the unit-type boiler-turbine generator plants. Data from portions of the operating periods for the 187 unit TVA system and the 14 unit ORGDP … more
Date: March 31, 1960
Creator: Myers, M. L. (Millard L.)
Partner: UNT Libraries Government Documents Department
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Estimate Of Potential Fuel Reprocessing, Revision #30 Part A

Description: The power and estimated reprocessing load are tabulated for existing and proposed for United States and United States-built reactors of 10 Kw or greater thermal power.
Date: March 15, 1960
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Contamination of Shipping Cask and Storage Canal Water By Fuels Irradiated In Pressurized Water Reactors - A Review Of Pertinent Subjects

Description: The subjects of fuel element failures, rates of release and re-deposition of radioactive materials from ruptured and intact fuel elements in pressurized water reactors, corrosion rates of fuels in canal water and in contact with pressurized water, activity in storage canal water, fuel meltdown studies, and decontamination are reviewed and evaluated in relation to the shipment and storage of irradiated fuel elements.
Date: March 17, 1960
Creator: King, L. J.
Partner: UNT Libraries Government Documents Department
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5-gpm In-Pile Thorium Oxide Slurry Loop Development, Runs 14 Through 16 In Loop L-4-248, And Filtration Of Thorium Oxide Slurry With Sintered Filters

Description: In in-pile pump loop capable of circulating thorium oxide slurry while exposed to nuclear radiation in an experimental reactor beam hole is necessary to obtain information on the effect of reactor radiation on the physical and chemical properties of the slurry and on the corrosion-erosion of containment materials. Thorium oxide filtration test results with various sintered-metal filters and one aluminum oxide filter are reported.
Date: March 7, 1960
Creator: Baker, J. M.; Jones, D. T. & Savage, H. C.
Partner: UNT Libraries Government Documents Department
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IBM 704 Gaussian-Integration Routines

Description: Three Gaussian-integration routines have been written for the IBM 704 and placed on the FORTRAN Library tape. 9These routines may be used singly or in combination to perform single, double or triple integration of any function within a FORTRAN program. Either fixed or variable integration limits may be used.
Date: March 14, 1960
Creator: Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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An Investigation Of Thermal Diffusion Separation Of U-232 - U-233 As An Alternate To Remote Processing

Description: Liquid phase thermal diffusion separation of U-232 - U-233 has been investigated as a possible alternative to remote processing. The calculations were based on a horizontal type thermal diffusion column operating 24 hours/day on the spent thorium fuel on one Consolidated Edison reactor, the latter producing 8 tons irradiated thorium/year.
Date: March 10, 1960
Creator: Jury, S. H.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor - A General Description

Description: This report is issued primarily to make available a general description which reflects the current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge National Laboratory.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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