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14-Year 113Cd

Description: The half lives of Cd/sup 113m/ and Cd/sup 115m/ have been redetermined to be 14 sintering time 2 years and 44.2 sintering time 0.5 days, respectively. The ratio of Cd/sup 113m/Cd/sup 115m/ yields from thermal-neutron fission of U/sup 235/ is 0.27 sintering time 0.03, and the ratio of (n, ) formation cross sections is 0.31 sintering time 0.03. Combination of these ratios with literature values for the Cd/sup 115m/ fission yield and (n, ) formation cross section gives (1.9 sintering time 0.2) x 1… more
Date: October 31, 1959
Creator: Wahl, Arthur C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Absorption of Organic Acids on Thoria

Description: The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date: December 31, 1959
Creator: Bradford, Harold R. & Wadsworth, Milton E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annual Report of Research Progress

Description: This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes… more
Date: December 31, 1959
Creator: Truell, Rohn, 1913-1968
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APPLIED HEALTH PHYSICS SEMI-ANNUAL REPORT FOR JULY 1956-DECEMBER 1956

Description: Routine monitoring procedures are summarized. Based on samples collected by continuous air monitors, the wcekly average value for air contamiration in the laboratory area was 1.98 x 10/sup -12/ mu c/cc. Radioactive fall-out was determined by measuring the total activity and total number of particles collected on gum paper fall-out trays. Two peak periods of activity in July and September were concluded to be the result of weapons tests. Meteorological data are tabulated. Data are included from … more
Date: October 31, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959

Description: Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date: December 31, 1959
Creator: Beck, Lyle Vibert, 1906-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Auctioneers TELOP]

Description: Photograph of a TELOP advertising auctioneers. A white box in the middle has a picture of a gavel with writing that says, "Wayne Cook Associates, Inc. 'the nation's leading auctioneers.'" On top of the box in small writing it says, "Contact." Below the box it says, "193 Meadows Building, Dallas 6, Texas, Tel. EM 3-3388." The TELOP is attached to a dark board.
Date: March 31, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Photograph
Partner: UNT Libraries Special Collections
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of the G Factor for Gas Scattering Experiments

Description: The "G factor'' relating the yield to the beam intensity, target density, and scattering cross section is calculated for several types of aperture boundaries. The case of a front aperture composed of two parallel edges of infinite height with a rear aperture of any shape is calculated up to terms in the fourth derivative of the cross section. (W.D.M.)
Date: October 31, 1959
Creator: Silverstein, Edward A.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for August 1959

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed by taking a macro photograph of the desired gradient by monochromatic (436 m mu ) light transmitted by the solution normal to the gradient in an appropriate diffusion cell. Two Druhm runs were terminated due to malfunction of the sodium metering system and the third run was terminated when the UF/sub 6/ nozzle ruptured. Calculations of particle temperature versus time relations for the flame denitration-cal… more
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[Commencement Program for North Texas State College, May 31, 1959]

Description: Commencement Program for North Texas State College in 1959. Printed on the cover are the words, "The Sixty-Ninth Annual Commencement of North Texas State College. Denton, Texas. Sunday, May Thirty Nineteen Hundred and Fifty-Nine at Eight O'Clock in the Evening Fouts Field." The program contains the order of service and a list of graduates for both the baccalaureate and master's degree.
Date: May 31, 1959
Creator: North Texas State College
Item Type: Refine your search to only Pamphlet
Partner: UNT Libraries Special Collections
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Control Rod Positions for Criticality. Section II. Fourth Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod configurations after 560 EFPH's of reactor operations are charted in the report.
Date: March 31, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Department of Chemical Engineering Progress Report for September 1, 1957 Through June 30, 1958. Part I. Thermal Conductivity of Deuterium Oxide

Description: The thermal conductivity of heavy water was found to vary from 0.345 at 105 deg F through a maximum of 0.375 at about 265 deg F to 0.371 at 339 deg F. The conductivity was determined by a steady-state method in a cylindrical apparatus having an over-all length of 11.35 inches and a liquid layer about 0.061 inch thick. A temperature drop of approximately one degree Fahrenheit across the liquid was maintained. The temperature drop was measured with thermistors. The apparatus was calibrated with l… more
Date: October 31, 1959
Creator: Baker, B. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Diffusion of Uranium with Various Transitional Metals; DIFFUSION DE L'URANIUM AVEC QUELQUES METAUX DE TRANSITION

Description: The diffusion process in uranium and its alloys was studied from 550 to 1075 deg C with diffusion couples of U with Zr, Mo, Ti, and Nb and with the alloys U--Nb and U--Mo. A brief description is given of the experimental methods. Results relative to the concentration-penetration curves are presented, and the coefficients of diffusion are calculated. The equilibrium diagram was established for the U--Zr system. The results obtained by micrographic examination, microhardness measurements, and aut… more
Date: October 31, 1959
Creator: Adda, Y. & Philibert, J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Indoleacetic Acid and Kinetin on the Growth of Some Microorganisms

Description: Data are presented from a study of the effects of indoleacetic acid and kinetin on the growth of Amoeba proteus, Escherichia coli, and two species of yeast. Data are tabulated and reaction mechanisms are discussed. 95 references. (C.H.)
Date: March 31, 1959
Creator: Kennell, D.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for December 1958 January- February 1959

Description: Design and construction are proceeding satisfactorily. Fuel capsule irradiation studies are progressing, and preparation of specifications for fuel elements and assemblies is almost complete. Other design, development, and construction progress is reported. Instrumentation developments are described. Reactor physics studies are reported. (For preceding period see AECU-4013.) (T.R.H.)
Date: October 31, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for March-April-May 1959

Description: An alternate design of the Elk River Reactor was completed during the quarter. Three points were emphasized in the study: performance capability to provide 116 Mw(th) output; fuel costs of the reference design versus alternate fuel media and cladding; and reactor control modifications to provide sufficient reactivlty to eliminate soluble hold down'' poisons, permit higher power operation and obtain a greater fuel life. Work is summarized on fuel element and material development progra… more
Date: October 31, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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