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909B high energy gull generator

Description: No Description Available.
Date: December 31, 1960
Creator: Stephens, W. H.
Partner: UNT Libraries Government Documents Department
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Adsorption of Radioactive Gases on Activated Carbon

Description: The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report for July 1, 1958 Through June 30, 1959

Description: The objective of the Applied Mathematics Division is to provide mathematical assistance to other scientists in the Lab. This goal is achieved by (1) conducting research in numerical analysis and other branches of mathematics, (2) providing mathematical consultation, and (3) operating a computational service, using both digital and analog machines. Publications, papers, seminars, lectures, and courses are listed. A summary listing of computer programs developed or in progress is given. (For prec… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report for July 1, 1959 Through June 30, 1960

Description: A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, AND MARCH 1957

Description: Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution of uranium-- zirconium fuel alloys continued. In corrosion tests to find a suitable container material, Ni was found to be susceptible to a sulfur-type attack. Hastelloy B showed promise, and graphite offers excellent chemical resistance but poor mechanical strength. The dissolution rate of Zr in NaF-- ZrF as affected by impingement of the HF sparge was studied. Production of UF/sub 6/ by fluidi… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1960

Description: Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Coolant backup design study basis and objective

Description: Preliminary studies have, in general, indicated the need for modifications and improvements to the reactor last ditch coolants systems in order to provide adequate safety of operation at power levels programmed for the future. These studies have indicated the need for improved reliability as well as increased capacity for the last ditch coolant systems. A design study is being prepared by Reactor Modification Design to define the scope of the modifications required to provide adequate last ditc… more
Date: August 31, 1960
Creator: Schack, M. H. & Tupper, W. J.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can bond separation following irradiation. Such evidence h… more
Date: August 31, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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DMM: A Multigroup, Multiregion, One-Space-Dimensional Computer Program Using Neutron Diffusion Theory. Part 1 - The Theory

Description: DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Calculations of fission-produced xenon and samarium and time variation due to production and depletion of isotopes are an essential part of this program. The adjoint fluxes may also be computed, and the program includes the calculation of the nuclear constaants from fairly simple input combined with a library of cross section… more
Date: December 31, 1960
Creator: Leshan, Edward J. & Kavanagh, Deveroux L.
Partner: UNT Libraries Government Documents Department
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DMM: A MULTIGROUP, MULTIREGION ONE-SPACE-DIMENSIONAL COMPUTER PROGRAM USING NEUTRON DIFFUSION THEORY. PART II. DMM PROGRAM DESCRIPTION

Description: Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Complete descriptions of the routines and problem input and output specifications are also included. (D.L.C.)
Date: December 31, 1960
Creator: Kavanagh, D.L.; Antchagno, M.J. & Egawa, E.K.
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for June-July-August 1959

Description: Progress is summarized on fuel element development, control rods and drives, reactor vessel and components. shielding, instrumentation, reactor building, plant facilities, and construction at site. (See also ACNP-ERR-3.) (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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Elk River Reactor Quarterly Project Report for September-October-November 1959

Description: With the project design work virtually complete, progress during the quarter consisted primarily of prccurement, fabrication of components, and construction at the reactor site. Developments are briefly summarized in the fuel element program, core physics vessel and internal components, control rods and rod drives, shielding, process, instrumentation, building and facilities, and construction. (For preceding period see ACNP-ERR-5.) (W.D.M.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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The Energy Gap in Nuclear Matter

Description: The magnitude of the energy gap in nuclear matter associated with a highly correlated ground state of the type believed to be important in the theory of superconductivity has been evaluated theoretically. The integral equation of Cooper, Mills, and Sessler is linearized and transformed into a form suitable for numerical solution. The energy gap, calculated by using an appropriate single-particle potential and the Gammel-Thaler two-body potential, is found to be a very strong function of the den… more
Date: January 31, 1960
Creator: Emery, V. J. & Sessler, A. M.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Data on Nuclear Carbides

Description: Data on the properties, constitution, compatibility, radiation behavior, fabrication, preparation, storage, and handling of uranium, thorium, and plutonium carbides are reviewed. 187 references. (C.J.G.)
Date: May 31, 1960
Creator: Rough, F.A. & Chubb, W. eds.
Partner: UNT Libraries Government Documents Department
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Fuel Element Catastrophe Studies Hazards of Fission Product Release From Irradiated Uranium

Description: The rate of reaction of highly irradiated U with air, CO/sub 2/, and steam was studied in sn investigation of the fission product release potential in a loss-of-coolant type accident postulated for Pu-producing reactors. Highly irradiated U was found to be more reactive, probably because of the defects in the oxide coating formed by the inclusion of fission products. Complete oxidation or melting was found to release rare gases, I, and Te semi- quantitatively in most atmospheres. Other fission … more
Date: October 31, 1960
Creator: Parker, G. W.; Creek, G. E.; Martin, W. J. & Barton, C. J.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Quarterly Progress Report for November 1, 1959 to January 31, 1960

Description: A variety of spherical uranium--graphite fuel elements for the Pebble Bed Reactor (PBR) was fabricated. Poor results with sintered alumina coated UO/ sub 2/ particles led to the development of slumina coating by vspor deposition, for which good results have been obtained. A variety of sub-surface metal, metal carbide, and ceramic coatings located between an unfueled graphite shell and the fueled core of a PBR fuel element was prepared and examined. Most of the materials and processes showed poo… more
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department
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