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Determination of Coefficients of Reactivity. Test Results DL-S-151 (T-550132). Section I. Fourth Performance

Description: The purpose of the test was to determine the temperature and pressure coefficients of reactivity at sere power. The value for the temperature coefficient at the operating temperature of 523 F with 556.6 EFPH plant operation was 2.5 (delta E/F) x 16(-4). The magnitude of the temperature coefficient at the plant operating temperature (523 F) indicated the reactor is very stable during normal operations. The pressure coefficient varied from values of 1.41(deltaE/psig) x 10(-6) at 1437 psig to a.57… more
Date: January 31, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Preliminary Design Study for a Sodium-Graphite-Reactor Irradiation Facility

Description: The results of an investigation to integrate a Na/sup 24/ irradiation processing facility with an operating sodium graphite reactor are presented. An irradiation facility incorporated into a reference SGR (Hallam Nuclear Power Facility, Hallam, Nebraska) is described. Development of the facility application, preliminary design criteria and capital and operating costs are discussed. Recommendations for further development of the technology and economics of this type of irradiation facility are i… more
Date: January 31, 1959
Creator: Thompson, D.S. & Benaroya, V.
Partner: UNT Libraries Government Documents Department
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Radiation Chemistry of Organic Substances. Final Report for 1 January 1957 to 31 January 1959

Description: The chemical processing of reactor fuels involves the use of organic substances as extracting agents and as diluents. When most organic substances ae exposed to reactor fuel, radiation damage occurs. The objectives of this project were to provide more information regarding damage to hydrocarbon solvents which are similar to those used as solvents in the Thorex program and to determine if the radiation-damaged diluent has a pronounced deleterious effect upon the extraction process.
Date: January 31, 1959
Creator: Knight, James A., Jr.
Partner: UNT Libraries Government Documents Department
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Station Start-up Test. Test Results DL-S-163 (T-554923). Section 1

Description: The purpose of the test was to determine the station operating characteristics during a start-up with all reactor coolant loops initially cold, requiring chemical addition and the turbine cold. The plant was successfully taken from a cold condition to generator synchronizing in accordance with Volume I, Chapter 43, Station Start-up no. 1. Twice during the test malfunctioning equipment delayed the completion of the test. The 1B boiler drum level indication required repair work and the 1D loop wa… more
Date: January 31, 1959
Creator: Eckenrode, Gerald E.
Partner: UNT Libraries Government Documents Department
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Estimate of the Fast Effect in the Lid Tank Source Plate

Description: An estimate was made of the fast effect in the lid tank source plate. The number of fast fissions per thermal fission is 0.019. (auth)
Date: March 31, 1959
Creator: Dresner, L.
Partner: UNT Libraries Government Documents Department
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Research and Investigation Leading to Methods of Generating and Detecting Radiation in the 100 to 1000 Micron Wavelength Range of the Spectrum. Quarterly Progress Report No. 11 for September 1, 1958 to December 1, 1958

Description: The purpose of this research is twofold: (a) To uncover new principles or techniques from which a CW source of electromagnetic radiation for the low millimeter and submillimeter wavelength range can be developed; (b) To develop suitable detectors, components and measuring techniques for evaluating and using the radiation as a diagnostic tool for plasma physics. The report gives present status of the work in (1) Ferrites; (2) Gas discharge multiplier; (3) New CW generation methods; and (4) Dete… more
Date: March 31, 1959
Creator: Coleman, P. D.; Baird, J. R.; Becker, R. C.; Hakki, B. W.; Stafford, J. J.; Strain, R. J. et al.
Partner: UNT Libraries Government Documents Department
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Development of Uranium Nitride-Stainless Steel Dispersion Fuel Elements

Description: In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compati… more
Date: July 31, 1959
Creator: Paprocki, S. J.; Keller, D. L.; Cunningham, G. W. & Foulds Jr., A. K.
Partner: UNT Libraries Government Documents Department
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Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Description: Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. I

Description: This report analyzes a linear, hard-core pinch tube built to examine tubes afflicted by small-scale instabilities evident from many observations.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. II

Description: This report describes a toroidal version of the hard-core pinch and the additional information it can obtain to what the analogous linear pinch can get.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. Part I

Description: It is well known that a pinch column with internal H/sub Z/ and external conducting shell can be made grossly stable, but that small-scale instabilities persist; especiaily in the tubular region of maximum current density. To investigate further these small-scale instabilities of the stabilized pinch,'' we are using 12-in.-i.d. linear pinch tube with a 3-in.-o.d. insulated center rod. By controlling a current along this rod, as well as a current along external conducting straps, and a third cur… more
Date: July 31, 1959
Creator: Birdsall, D.H.; Colgate, S.A. & Furth, H.P.
Partner: UNT Libraries Government Documents Department
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THE HARD-CORE PINCH. PART II

Description: The toroidal version of the hard-core pinch tube is created by levitating a ring conductor inside a toroidal shell. The magnitude of induced H/ sub theta / necessary for levi-tation is small in terms of field strengths normally desired for energetic pinches. In a 3-in. glass-and-copper toroid of square cross section a 3/4-in. hollow copper ring has been levitated with a 60- cycle current of 3 kiloamperes. A 12-in stainless steel tube of round cross section is being built. The stability of nearv… more
Date: July 31, 1959
Creator: Birdsall, D.H.; Colgate, S.A. & Furth, H.P.
Partner: UNT Libraries Government Documents Department
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PRTR Total Energy Distribution Calculations

Description: Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, util… more
Date: July 31, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, and Boron Carbide Compatibility With Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000 to 12OO deg C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated an… more
Date: July 31, 1959
Creator: Cherubini, J. H. & Leitten, C. F. Jr.
Partner: UNT Libraries Government Documents Department
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CALCULATION OF RADIAL NEUTRON-FLUX DISTRIBUTION IN EGCR LATTICE CELL

Description: The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriched uranium odde were obtained by using a one- velocity, one-dimensional P-3 solution to the neutron transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experiments and calculated distributions. Flux traverses in the outer rod perpendicular to diameter of the cluster are also presented. (auth)
Date: August 31, 1959
Creator: DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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Calculation of Radial Neutron-Flux Distribution in EGCR Lattice Cell

Description: The Neutron-flux distributions in an EGCR cell containing seven rod clusters of 2.0 and 2.6% enriched uranium oxide have been obtained by using a one-velocity, one-dimensional P-3 solution to the neutron-transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experimental and calculated distributions. Flux traverses in the outer rod perpendicular to a diameter of the cluster are also presented.
Date: August 31, 1959
Creator: DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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Californium Production in the High Flux Isotope Reactor

Description: Californium-252 and other isotope production rates resulting from irradiating Pu-242 in the proposed High Flux Isotope Reactor were estimated. The effect of curium recycle was investigated and optimum irradiation cycles determined.
Date: August 31, 1959
Creator: Claiborne, H. C. & Lietzke, Marjorie P.
Partner: UNT Libraries Government Documents Department
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Decomposition of Nitrous Oxide Final Report. Period Covered: February 19, 1959-August 18, 1959

Description: The decomposition of N/sub 2/O in a reactor tube containing various fixed-bed catalysts was investigated at 200 to 700 deg C, space velocities of 250, 1250, and 2500 vol. of gas per vol. of catalyst per hr, and various gas mixture compositions. As catalysts, En at 500 deg C and Pd at 650 deg C both gave satisfactory results. NO/sub 2/ was formed with all these catalysts, the amount increasing as the residual N/sub 2/O decreased. (C.J.G.)
Date: August 31, 1959
Creator: Zufall, J. H. & Miller, H. S.
Partner: UNT Libraries Government Documents Department
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Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion

Description: The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown t… more
Date: August 31, 1959
Creator: Dillon, R.L.
Partner: UNT Libraries Government Documents Department
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Molten Salt-Graphite Compatibility Test. Results of Physical and Chemical Measurements

Description: The observed changes in dimensions, weight, and chemical composition of "impervious" graphite rods in contact for a year with flowing liquid LiF-BeF2-UF4, (62-37-1 mole %) in a pump loop at 1300'F are listed.
Date: August 31, 1959
Creator: Sheil, R. J.; Evans, R. B. & Watson, G. M.
Partner: UNT Libraries Government Documents Department
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New Production Reactor Thermal Shielded Studies

Description: The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
Partner: UNT Libraries Government Documents Department
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