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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design crit… more
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equati… more
Date: May 25, 1959
Creator: Alexander, L G
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of … more
Date: May 25, 1959
Creator: Alexander, L. G.
Partner: UNT Libraries Government Documents Department
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Allis-Chalmers Critical Facility: Final Safeguards Report

Description: Report discussing the final safeguards integrated into the design of the Pathfinder Atomic Power Plant for the Northern States Power Company. The plant is designed by the Allis-Chalmers Manufacturing Company in Greendale, Wisconsin. Description of the facility, operating procedures, experiments, accident analysis, safety features of the reactor, and make up of the surrounding area are included.
Date: May 1, 1959
Creator: Allis-Chalmers Manufacturing Company
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 11, Number 9, May 1959

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: May 1959
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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PROBLEMS IN ACCOUNTABILITY MEASUREMENTS ASSOCIATED WITH THE INTERIM CHEMICAL PROCESSING PROGRAM

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarized. Experienee in comparisons of reactor (production and research) calculations vs. chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions ( plus or minus 0.54 to plus or minus 0.78%) in chemical plant measurements (bulk and analytical) for fissionable material accountab… more
Date: May 28, 1959
Creator: Arnold, E D & Gresky, A T
Partner: UNT Libraries Government Documents Department
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Problems in Accountability Measurements Associated with the Interim Chemical Processing Program

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precis… more
Date: May 28, 1959
Creator: Arnold, E. D. & Gresky, A. T.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

Description: This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
Partner: UNT Libraries Government Documents Department
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CALCULATION OF GROUP CROSS SECTIONS FOR HOT MONOATOMIC MODERATOR WITH VARIABLE FLUX WEIGHTING WITHIN GROUPS, 704 CODE 521/RE 145

Description: This code finds inelastic cross-section matrix elements (transfer matrix) for hot monatomic moderator for multigroup calculations by numeric- analytic double integration of Cohen's formula. Several approximations to the actual neutron density ean be used as weight functions over the velocities of the initial groups. Modified and supplemented results are presented on binary cards and/or tape for direct input into the Argonne Transport Theory Codes or the SNG Code, or for offline output. (auth)
Date: May 1, 1959
Creator: Bareiss, E.H.; Denes, J.E. & Jankus, V.Z.
Partner: UNT Libraries Government Documents Department
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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exp… more
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Partner: UNT Libraries Government Documents Department
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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fall-out. Pocket ionization chambers were used for measurement of the radiation-field strength. Fall-out was simulated with distributed and point-source configurations of Co/sup 60/ and Ir/sup 192/ sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with ex… more
Date: May 1, 1959
Creator: Batter, Jr., J. F.; Kaplan, A. L. & Clarke, E. T.
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Monitoring Program. Progress Report No. 6 Covering period November 1, 1958 to January 31, 1959. Report No. 1903

Description: Programs of research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication, and calibration of balloon-borne particle sampling equipment to implement the precise determination of stratospheric particle concentration and particle size distribution are reported. A two-stage rectangular jet impactor which collects airborne particles by impingement on a flat plate and is designed to obtain data on size distribution was fabricated.… more
Date: May 1, 1959
Creator: Baumstark, J;; Torgeson, L;; Stern, S;; Schekman, A; & Zeller, W
Partner: UNT Libraries Government Documents Department
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Preparation of Pitch-Soluble Uranyl-Organic Compounds

Description: Batch processes on a scale of 250 to 300 g of uranium were developed for the production of uranyl oxinate (8quinolinate) and uranyl malonate. Both compounds are insoluble in water and were found to be suitably soluble in pitch. Uranyl oxinate was prepared by the reaction of an aqueous uranyl nitrate solution with an acetic acid solution of oxine (8-quinolirol) at about 80 deg C. Complete precipitation was accomplished by the addition of ammonium hydroxide. Yields of better than 99.5% were obtai… more
Date: May 1, 1959
Creator: Baxman, H. R.; Jackson, D. D.; Williams, D. L. & Bard, R. J.
Partner: UNT Libraries Government Documents Department
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NONDESTRUCTIVE TESTING OF EBR-I MARK III FUEL ELEMENTS AND COMPONENTS

Description: Ultrasonic and eddy current methods were used to inspect EBR-I Mark III fuel elements and componentsUltrasonic techniques were used to inspect for homogeneity of the casting, bonding of the core to the clad on the extruded rod, bonding of the Zircaloy spacer disk to the uranium, and cracks in the Zircaloy rod used for end caps. Eddy current techniques were used to measure the cladding thickness on the extruded rods and to inspect the zirconium wire used for spacers on the completed fuel element… more
Date: May 1, 1959
Creator: Beck, W.N.; Renken, C.J.; Myers, R.G. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department
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Preliminary report on radioactive mineral deposits in the Gulf Coastal Plain of Texas and Louisiana, north and east of the Guadalupe River

Description: "Approximately 30 radioactive mineral deposits are known to occur in the Gulf Coastal Plain of Texas and Louisianna, north and east of the Guadalupe River. A preliminary field examination and sampling of each deposit has been made"
Date: May 1959
Creator: Blair, Robert G.
Partner: UNT Libraries Government Documents Department
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Scram transient tests PT-IP-249-C

Description: The purpose of this production test is to provide a standard method of obtaining scram transient reactivity information at the eight reactors, under conditions conducive to valid data. These conditions include the bypassing of the Panellit system at a low power level for a short, controlled period of time during May 1959.
Date: May 25, 1959
Creator: Bowers, C.E.
Partner: UNT Libraries Government Documents Department
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THE DEVELOPMENT OF A FLUIDIZED BED REACTOR FOR THE FLUOROX PROCESS: UNIT OPERATIONS MONTHLY STATUS REPORTS FOR THE PERIOD NOVEMBER 1958 THROUGH MAY 1959

Description: Results of four experimentul runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF/sub 6/ production from UF/ sub 4/ by use of dry air of O/sub 2/, 2UF/sub 4/ + O/sub 2/ = UF/sub 6/+ UO/sub 2/ F/sub 2/, in an Inconel fluidized bed reactor at 800 to 850 deg C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF/sub 6/ was collected or measured. Two runs made with crude UF/sub 4/ (produced from unpurified m… more
Date: May 26, 1959
Creator: Bresee, J C; Horton, R W & Scott, C D
Partner: UNT Libraries Government Documents Department
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