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UO2 Fuel Cluster Study

Description: The reactor physics aspects of a number of different UO2 cluster geometries were determined as a function of various parameters. These parameters included number of rods in cluster, cladding materials, cladding thickness, cored and uncored rods, lattice pitch, rod size, and inter-rod spacing. Lifetime calculations were made on the basis of batch loading and uniform exposure for 5000 and 7500 Mwd/MT-UO2.
Date: December 31, 1959
Creator: Delene, J. G. & Row, T. H.
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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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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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Handling, Service and Waste Disposal Buildings Drain Test. Section I. Test Results DL-S-230 (T-641115)

Description: The purpose of the test was to prove the integrity of the non-active drains, the special drains, the sanitary drains, the chemical waster drains and the storm water drains by means of a water flow test and visual inspection. The two roof boxes and the one floor drain of 1B Auxiliary Equipment Room did not drain properly. The lab sink in the west end of the Radiochemistry Lab drained to the Special Monitored West Transfer Tank instead of the Monitored Waster Transfer Tank. All other drains funct… more
Date: March 31, 1959
Creator: Barclay, Richard E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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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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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Functions of Aging. Insolubilization of Protein as a Function of Aging. Final Report

Description: Whole-body x irradiation was used to accelerate the onset of senescence in female white rats. Comparisons of nonirradiated and irradiated tissues have been made using histological, physical, and enzyme techniques. The data amassed to date indicate that x irradiation causes a reduction of 20.6 percent in alpha- amino nitrogen liberated by tryptic hydrolysis in liver homogenates. This reduction in amino nitrogen is not observed, however, in muscle homogenates. Shrinkage temperature determinations… more
Date: March 31, 1959
Creator: Bjorksten, Johan, 1907-; Andrews, Fred A.; Trenk, Bruce & Bailey, Julia
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Proceedings of an Informal Discussion on the Radiation Chemistry of Water, January 8-9, 1959

Description: A report of discussions on radiation chemistry prepared from the editor's notes is presented. Included are sections on the present state of radiation chemistry of water, recent developments in theory, radiolysis of water in the solid state, electron capture and negative ion formation, new experimental techniques, and cube root law. (J.R.D.)
Date: October 31, 1959
Creator: Bünau, Günther von; Kurien, K. C.; Taylor, W. H. & Theard, L. M.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanisms of Surface Adsorption in Homogeneous Reactor Loops. Semi- Annual Report No. 2 for 1 July to 31 December, 1957

Description: Homogeneous reactor operating conditions in which solids and deposits are formed on loops were examined. Methods of removing existing deposits are also considered. Experiments were conducted to study the characteristics of solids and deposits on type-347 stainless steel and on Zircaloy-2 specimens using simulated homogeneous reactor solutions in a rocking autoclave. Ferric and chromic sulfate were added to the solution in some of the tests to form solids by hydrolysis. Four tests were run at 30… more
Date: October 31, 1959
Creator: Eding, H. J.
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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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.
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 September-October-November 1958

Description: Design and construction are proceeding on schedule. Physics and shielding calculation results are reported and discussed. Studies of the high- pressure B injection safety system are described. The programs for fuel element and materials development, reactor vessel and internal components, process and superheater, reactor building and plant facilities, and instrumentation are outlined. (For preceding period see AECU-3991.) (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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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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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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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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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
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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