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Metabolism and Distribution of Inhaled Plutonium in Rats

Description: From abstract: "Several different techniques were used to introduce tracer quantities of plutonium into the lungs of rats. When aerosols were produced by atomizing aqueous solutions of the nitrates it was found that approximately 20 per cent of the dose was absorbed and deposited in the skelton [sic] with tetra-, hexa-, and trivalent plutonium. Thus with these compounds, the lungs represent a more dangerous portal of entry than either oral (0.05 per cent) or intramuscular (13 per cent) administ… more
Date: October 29, 1946
Creator: Abrams, Richard; Siebert, H. C.; Potts, A. M.; Forker, L. L.; Greenberg, D.; Postel, A. et al.
Partner: UNT Libraries Government Documents Department
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Review of Potential Host Rocks for Radioactive Waste Disposal in the Southeast United States, Southern Piedmont Subregion

Description: From abstract: "A literature study was conducted on the geology of the Southern Piedmont province of the states of Maryland, Virginia, North Carolina, South Carolina, and Georgia. The purpose was to identify geologic areas potentially suitable for containment of a repository for the long-term isolation of solidified radioactive waste."
Date: October 1980
Creator: Acres American Incorporated
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: September 1966

Description: Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Mercury Cooled Breeder Reactors

Description: Abstract: The technical feasibility and economic potential of fast breeder power reactor systems cooled with boiling mercury have been investigated by American-Standard under the United States Atomic Energy Commission's New Reactor Concepts Evaluation Program.
Date: October 13, 1959
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department
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Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator

Description: Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date: October 19, 1961
Creator: Allen, Charles F.
Partner: UNT Libraries Government Documents Department
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Results of Preliminary Drilling, Red Rock, Arizona

Description: Abstract: Structure drilling under Contract No. AT(05-l)-120 was begun May 13, 1951, and was suspended June 30, 1951, at Red Rock, Arizona with the completion of 12 holes and 2,390.5 feet of drilling. No mineralization was disclosed in the widely spaced holes. The structure and rock composition was found favorable for a potential drilling area.
Date: October 16, 1952
Creator: Anderson, Andrew H.; Foster, John R. & Hurley, Daniel B.
Partner: UNT Libraries Government Documents Department
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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Partner: UNT Libraries Government Documents Department
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Reference Flat Pulse Generator

Description: Introduction: A reference step-like pulse generator is described which has been developed at NBS. This generator can be used for accurately characterizing the step response of various kinds of trap ient recording equipment (oscilloscopes, waveform recorders, transient digitizers, etc.). Basic design principles are given as well as complete circuit diagrams and descriptions. An analysis of the output stage of the generator is presented together with the circuit models for developing a time-domai… more
Date: October 1983
Creator: Andrews, J. R.; Bell, B. A. & Baldwin, E. E.
Partner: UNT Libraries Government Documents Department
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Radiocarbon from Pile Graphite; Chemical Methods for its Concentration

Description: Abstract. Samples of pile graphite, irradiated in a test-hole at Hanford for 15 months, have been assayed for radioactive C14, yielding 0.38 ± 0.04 microcuries per gram. At this level of activity, the pile graphite contains very valuable amounts of C14. The relation between the above assay and the probable average assay of pile graphite is discussed, and it is concluded that the latter is almost certainly above 0.3 uc/ gram. Controlled oxidation of this graphite, either with oxygen at ~ 750°C,… more
Date: October 10, 1946
Creator: Arnold, James R. & Libby, Willard F.
Partner: UNT Libraries Government Documents Department
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Radio-micrography as a Tool in Biological Investigation

Description: The technique of radio-micrography has been discussed. The necessary equipment has been described. Its applications with examples and comparison with other more conventional techniques have been pointed out.
Date: October 31, 1952
Creator: Askin, J E. C.; Yates, L L; Cauldwell, E W. & Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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A Study of the Carrier Distillation Excitation of Iron in U3O8

Description: Abstract: "A radioactive tracer, Fe^59, was used to determine the disposition of iron as a result of the excitation of a U3O8 matrix in a d - c arc. Two different spectrographic procedures, both using carrier distillation excitation techniques, were compared as to the percent of iron volatilized, the percent of iron diffused into the electrode and the percent of iron remaining in the residual charge."
Date: October 1, 1957
Creator: Atwell, M. G. & Pepper, C. E.
Partner: UNT Libraries Government Documents Department
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Analysis of Uranium-Manganese Alloys

Description: Introduction. the conventional procedures of analysis for uranium and manganese can be employed in the analysis of alloys of these metals. The alloys are reacted with perchloric acid and hydrogen peroxide, fumed to remove any chloride ions, diluted to volume and aliquots analyzed by redoximetry.
Date: October 5, 1945
Creator: Ayers, A. S.
Partner: UNT Libraries Government Documents Department
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Precipitation of Thorium Oxalate from Nitric Acid Solutions

Description: Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended … more
Date: October 5, 1945
Creator: Ayers, A. S.
Partner: UNT Libraries Government Documents Department
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Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

Description: From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
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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Metallurgical Aspects of SRE Fuel Element Damage Episode

Description: Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
Partner: UNT Libraries Government Documents Department
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Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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Separations Chemistry, Quarterly Progress Report, April-June 1954

Description: "Scale-up experiments on high temperature fuel recovery processes have included the dummy run phase on the handling of 1-kologram samples of molten, non-irradiated uranium in the hot cell. The next step involves the use of spent X-10 fuel slugs. Small scale experiments with X-10 uranium on the extaction of Pu with Mg show that as much as 80 per cent of the Pu can be removed in pone pass. Treatment of uranium with fused fluorides can remove at least 90 per cent of the Pu in one pass. Oxide sc… more
Date: October 1, 1954
Creator: Bareis, David W.; Cubicciotti, Daniel D. & Motta, E. E.
Partner: UNT Libraries Government Documents Department
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Direct Current Electromagnetic Pumps

Description: Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."
Date: October 25, 1949
Creator: Barnes, A. H.; Smith, F. A. & Whitham, G. K.
Partner: UNT Libraries Government Documents Department
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Progress Report for the Month of October, 1947 : Contract No. W-38-094-eng-27

Description: This report for October, 1947 describes progress regarding ore dressing and pyrometallurgical studies, chemical work on phosphates, chemical work on shales, and analytical work.
Date: October 30, 1947
Creator: Bearse, A. E.; Center, E. J.; Pray, H. A.; Richardson, A. C. & Sullivan, John D.
Partner: UNT Libraries Government Documents Department
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The Scandium-Yttrium and Scandium-Zirconium System

Description: Technical report. From Abstract : "The scandium-yttrium and scandium-zirconium were studied by thermal and x-ray methods. Both systems are characterized by complete solid solubility in the low temperature hexagonal form and in the high temperature bcc form. In the Sc-Y system, there is a minimum in the solidus at 50 at. pct and 1365°C, while the solidus in the Sc-Zr system follows a nearly straight line relationship between the melting point of scandium and zirconium. There is a minimum in the … more
Date: October 26, 1962
Creator: Beaudry, B. J. & Daane, A. H.
Partner: UNT Libraries Government Documents Department
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The Equation of State of Solids at Low Temperature

Description: Technical report describing and evaluating the the three experimental methods for obtaining equation of state data at low temperatures; (1) approximate measurement of the PVT relationship by a piston-displacement technique, (2) the measurement of a heat capacity at constant volume as a function of molar volume and temperature, and (3) direct measurement of the pressure variation of the elastic constants using ultrasonic techniques. X-ray methods also might be applicable.
Date: October 13, 1961
Creator: Bernardes, N. (Newton), 1931- & Swenson, C. A.
Partner: UNT Libraries Government Documents Department
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