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The Boron-Carbon System. Quarterly Report No. 3, November 1, 1960-January 31, 1961

Description: A definitive investigation of the boron-carbon equilibrium system is being made by x-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallogaphic and x-ray-diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 at.% carbon at 1500 to 2000 deg C. The melting point of the carbide-graphite eutectic was established as 2325 to 2350 deg C. No reversible allotropy of the beta -rhombohedral structure was observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 to 2050 deg C). No metallogaphic evidence of a three-phase reaction of dilute alloys is observed. (auth)
Date: February 1, 1961
Creator: Elliott, R. P.
Partner: UNT Libraries Government Documents Department
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BUILDUP OF Cf$sup 252$ AND INTERMEDIATE ISOTOPES FROM Cm$sup 244$ IN A HIGH FLUX

Description: The amount of Cf/sup 252/ and intermediate isotopes which could be made from Cm/sup 244/ in a reactor with high neutron flux was calculated. The variations of different isotopes formed in the bombardment as a function of time are described by a series of linear differential equations. The cross sections used were either weighed measured values or values estimated from the amounts of curium and californium isotopes formed in irradiations of heavy elements. The number of atoms of heavy curium isotopes per initial Cm/sup 244/ atom is given as a function of total flux intervals. The buildup of Bk/sup 249/ and the californium isotopes is also shown. (M.C.G.)
Date: February 1, 1961
Creator: Vandenbosch, S.E. & Fields, P.R.
Partner: UNT Libraries Government Documents Department
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CHEMISTRY DIVISION ANNUAL REPORT, 1960

Description: Summaries are given of the activities of the Nuclear Chemistry Division during 1960, in radioactivity and nuclear spectroscopy, fission, nuclear reactions, physical chemistry, instrumentation, and chemical engineering. Included are abstracts of graduate theses awarded during 196O for work conducted in the Division. (B.O.G.)
Date: February 1, 1961
Partner: UNT Libraries Government Documents Department
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A Condenser for the Vacuum Distillation of Metals

Description: A condenser, suitable for use in the distillation of metals was designed. The temperature of the condensing surface was established by controlling the pressure over boiling NaK-78 contained within the condenser. Performance was evaluated in test units in which pure bismuth was distilled as the test metal. (auth)
Date: February 1, 1961
Creator: Burnet, G. & Buchanan, W.
Partner: UNT Libraries Government Documents Department
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A CONTRIBUTION TO THE STUDY OF THE REDUCTION OF UF$sub 4$ TO URANIUM METAL

Description: Reduction of small charges of uranium tetrafluoride with magnesium proved to be successful. By hand-tamping of UF/sub 4/-- Mg blend, tap densities ranglng between3.1 and 3.4 g/cc were obtained. The reduction yields for these densities ranged from 72.79 to 93.71%. In the case of machinecompacted UF4-- Mg blend having tap densities from 3.58 to 3.68 g/cc, reduction yields were higher, ranging between 91.45 and 97.2%. Machine-compacted blends gave much more uniform temperature distribution curves during the preheating period, as a result of higher tap densities. The best yields were obtained by firing a machine- compacted blend containing 5% Mg excess at a furnace temperature of 650 deg C, giving an average crude metal yield of 96.3%. However, the high carbon content of 174 ppm in the crude uranium biscuits obtained by compacts reduction, as a result of hydrocarbon binder presence, appeared to be a disadvantage. Attempts were also made to demonstrate the initiation of the reduction reaction at temperatures lower than 500 deg C by taking x-ray-diffraction patterns of the samples of the UF4-- Mg charges heated up to various temperatures. (auth)
Date: February 1, 1961
Creator: Milosavljevich, J. & Baird, J.
Partner: UNT Libraries Government Documents Department
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Design and Construction of a Unit for Measuring Metal Skin Temperatures

Description: From summary: This report concerns the theoretical evaluation and experimental development of special thermocouples capable of being accurately located at or near the surface of metal structures to permit measurement of temperature distribution through the strictures.
Date: February 1961
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF METHODS FOR THE REFABRICATION OF EBR-II FUEL ELEMENTS. PART I. ENGINEERING CONSIDERATIONS FOR EBR-II FUEL REFABRICATION. PART II. DEVELOPMENT OF INJECTION CASTING METHODS AND EQUIPMENT. PART III. DEVELOPMENT OF FUEL PIN PROCESSING METHODS AND EQUIPMENT. PART IV. ASSEMBLY, WELDING, AND LEAK TESTING EBR-II FUEL RODS. PART V. DODIUM BONDING AND BOND TESTING EBR-II FU

Description: The development of remote fabrication methods and equipment in which the cooling periods, chemical fission product separation, and complete decontamination of the fuel is not required is discussed. A process designed around precision casting in multiple, glass molds served as a basis for design of refabrication equipment. The injection casting process is used. Procedures and equipment were developed for the remote manufacture of right-cylindrical, uranium alloy fuel pins from the castings. Assembly, welding, and leak testing of the EBR-II fuel rods are described. Methods of sodium bonding and bond testing are described. (M.C.G.)
Date: February 1, 1961
Creator: Shuck, A.B.; Ayer, J.E.; Jelinek, H.F.; Iverson, G.M.; Carson, N.J. Jr.; Brak, S.B. et al.
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments. Experimental Program, Experimental Procedures and Safety Considerations

Description: Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described. (M.C.G.)
Date: February 1, 1961
Creator: Kock, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Description: Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.)
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
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EBWR CORE 1A PHYSICS ANALYSIS

Description: The studies were primarily directed toward selection of the optimum loading for Core lA and a prediction of its properties. Included are analyses of some relevant experiments on Core 1, and prelimlnary modifications of Core 1 to Core lA. The factors which must be considered for the optimum loading determination are discussed. Four different loading pattenrs were investigated, which were considered to span the numerous possibilitles. Adequate cold shutdown was found to be almost unobtainable without the use of boric acid. For this reason, and because the heat transfer and stability limitations are severe, greater weight was given to heat transfer as opposed to control requirements. The use of boron-stainless steel poison strips fastened to the sides of the spike elements is considered insofar as in improving the loading from either the heat transfer or control standpoint. The relatlve advantages and disadvantages of the use of stainless steel fuel followers as opposed to Zircaloy followers are discussed. (B.O.G.)
Date: February 1, 1961
Creator: Avery, R.; Almenas, K.; Carson, C.; Iskenderian, H. & Kelber, C.
Partner: UNT Libraries Government Documents Department
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The Effect of Irradiation on Siliconized-Silicon Carbide Coatings for Graphite

Description: The results of an investigation into the effect of irradiation on the quality and integrity of several commercial siliocnized-silicon carbide (Si-- SiC) coatings for graphite are summarized. Si-- SiC-- coated graphites were oxidationtested at 1000 deg C in air both before and after irradiation. Data show that base graphites for coating must be fairly isotropic and must be stable toward high temperature radiation damage if the coating is to survive in-reactcr conditions. (auth)
Date: February 1, 1961
Creator: Jackson, J. L.
Partner: UNT Libraries Government Documents Department
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Engineering Applications of Analog Computers

Description: Six examples are given of the application of analog computers in the fields of reactor engineering, heat transfer, and dynamics: deceleration of a reactor control rod by dashpot, pressure variations through a packed bed, reactor kinetics over many decades with thermal feedback (simulation of a TREAT transient), vibrating system with two degrees of freedom, temperature distribution in a radiating fin, and temperature distribution in an irfinite slab with variable thermal properties. (D.L.C.)
Date: February 1, 1961
Creator: Bryant, L. T.; Janicke, M. J.; Just, L. C. & Winiecki, A. L.
Partner: UNT Libraries Government Documents Department
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Equations of State for Evolution Studies of Supernovae

Description: Tables of the energy, pressure, and chemical composition for a stellar mixture, originally a pure Fe/sup 56/, are presented as functions of temperature and density. They cover a range of conditions pertinent to the evolution of supernovae, involving the deconiposition of iron into helium plus neutrons, and the later stage of decomposition of helium into neutrons and protons. Relativistic degeneracy of electrons is included in these calculations. (auth)
Date: February 1, 1961
Creator: Grasberger, W. H. & Yeaton, J. B.
Partner: UNT Libraries Government Documents Department
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Frequency of Earthquakes for Selected Areas in the Western United States for the Period 1945-59

Description: The following report covers earthquake frequency data for the period 1945-59 for the states of California, Nevada, Washington, Montana, Wyoming, Utah, Arizona, and New Mexico. Additionally, it presents earthquake-frequency data for 100-mile square areas in California, Nevada, Washington, and Montana-Wyoming.
Date: February 1961
Creator: Twenhofel, W. S.; Black, R. A. & Balsinger, D. F.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report on the Juggernaut Reactor

Description: The Juggernaut is a light-water-cooled and moderated, graphite- reflected, heterogeneous thermal reactor designed to provide experimental facilities for conducting basic research in the neutron flux range to 4 x l0 n/cm/ sec at an operating power level of 250 kw(t). Pertinent design and operating characteristics are tabulated. Evaluations are made for potential hazards posed by certain hypothetical major accidents during the operation, and the adequacy of the safeguards provided to insure that the health and safety of personnel, within and beyond the site boundary, are not unduly endangered. The results indicate that in the event of any conceivable reactivity increase, auxiliary and inherent safety features pecuIiar to the Juggernaut will operate to insure automatic shutdown through a nondestructive BORAX-type process. (B.O.G.)
Date: February 1, 1961
Creator: Folkrod, J. R.; Moon, D. P. & Saluja, J. F.
Partner: UNT Libraries Government Documents Department
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THE HEAT TREATMENT OF PLUTONIUM

Description: Two groups of plutonium bars, one group containing 165 ppm iron and the other 678 ppm iron were end-quenched from the beta, gamma, delta, delta-prime, and epsilon phases. In general, cooling rate was found to have three striking effects on microstructure. The alpha grain size was found to decrease with increasing cooling rate during cooling from all phases. Upon cooling high-iron plutonium from the epsilon phase, the size of the Pu--Pu6/sub 6/Fe eutectic network decreased with increasing cooling rate. Cooling high-iron plutonium from temperatures between 413 and 460 deg C produced a wide variety of Pu --Pu/sub 6/ Fe configurations in the microstructure. Finally, the size of an unidentified spheroidal inclusion, soluble in the delta and higher temperature phases, decreased as cooling rate increased across the delta to gamma transformation. These effects of cooling rate can be used to indicate the cooling rate or thermal history that a particular plutonium specimen has encountered. A linear relationship between the alpha grain size and the Pu--Pu/sub 6/Fe eutectic network size was observed. The network size was roughly two times larger than the alpha grain size. Hardness traverses on each of the bars indlcated no apparent effect of coollng rate during quenchlng on hardness. A density decrease was noted near the quenched end of both low and high-iron bars which lndicated that faster cooling rates promote microcracklng. However, a greater decrease in density was obtained for the low-iron bars which was attributed to their greater tendency to microcrack. The presence of the Pu--Pu/sub 6/Fe eutectic network in the high-iron bars inhibits microcracking. (auth)
Date: February 1, 1961
Creator: Gardner, H.R.
Partner: UNT Libraries Government Documents Department
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HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date: February 1, 1961
Creator: Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner: UNT Libraries Government Documents Department
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Initial Peak Surge Current Detection Circuits

Description: Test requirements for several components specifies that surge currents be monitored to determine if the initial peak surge current exceeds a certain predetermined amplitude. This report describes and evaluates two circuits which were developed by Organization 2451 to meet this requirement in production testing.
Date: February 1961
Creator: Conrad, Milo M.
Partner: UNT Libraries Government Documents Department
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