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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.
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
Partner: UNT Libraries Government Documents Department
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Interpretation and Evaluation of the Uranium Occurences Near Goodsprings, Nevada: Final Report

Description: Abstract: The uranium occurrences near Goodsprings, Clark Co., Nevada, are divided into two distinct types which differ from each other in geographic distribution, localization of mineralization, mineralogy and origin. None of the known deposits is of present commercial significance and therefore this study emphasizes the genetic rather than the economic aspects.
Date: December 31, 1954
Creator: Barton, Paul B., Jr. & Behre, Charles H., Jr.
Partner: UNT Libraries Government Documents Department
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A Conceptual Study of a 100 kw Gas Cooled Reactor Power Plant for a Remote Location

Description: From introduction: This report details the conceptual design of a 100 kw gas cooled reactor power plant of the type that would satisfy the electrical and space heating load of the Air Force distant early warning stations and might find application at other remote bases.
Date: May 31, 1955
Creator: Frankfort, J. H. & Thompson, W. I.
Partner: UNT Libraries Government Documents Department
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Test of Buried Structural-Plate Pipes Subjected to Blast Loading

Description: Abstract: Two 20-foot-long, 7-foot-diameter, 10-gauge structural-plate pipes having longitudinal joints with 8 bolts per foot were buried and tested in the Smoky event of operation Plumbob at nominal predicted pressure levels of approximately 170 and 195 psi.
Date: December 31, 1958
Creator: Williamson, R. A.
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Partner: UNT Libraries Government Documents Department
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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
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The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
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.
Partner: UNT Libraries Government Documents Department
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Thorium Isotopes Method for Dating Marine Sediments

Description: This thesis is concerned with a possible method of improving the well-known ionium method of age determination of deep-sea sediment sections (Pet-53, Zou-58, Kul-55, Ran-54) both with respect to accuracy of individual determinations and with respect to the range of applicability of the method.
Date: May 31, 1960
Creator: Almodóvar, Ismael
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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Hydrogeochemical and Stream Sediment Detailed Geochemical Survey for Lakeview, Oregon

Description: Results of the Lakeview detailed geochemical survey are reported. Field and laboratory data are reported for 231 groundwater, 881 stream sediment, and 303 stream water samples. Statistical and areal distributions of uranium and possible uranium-related variables are displayed. A generalized geologic map of the area is provided and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed.
Date: May 31, 1980
Creator: Butz, T. R.; Tieman, D. J.; Vreeland, J. L.; Bard, C. S.; Leimer, H. W.; Helgerson, R. N. et al.
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.
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.
Partner: UNT Libraries Government Documents Department
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Progress Report No. 53 for the Period June 1, 1958 through October 31, 1958

Description: This is the fifty-third progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress reported covers the period, for Physics, June 1, 1958 through August 31, 1958; and for Chemistry, June 1, 1958 through October 31, 1958. Progress is reported on the following areas: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) High energy accelerator physics g… more
Date: October 31, 1958
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.
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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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.
Partner: UNT Libraries Government Documents Department
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