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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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1B HEAT EXCHANGER LEAK TEST. CORE I, SEED 1. Test Results

Description: Descriptions are given of various procedures used in determining leaks in the tubes of the 1B heat exchanger. Air pressurization tests determined leakage and leak rate of nine tubes. The leak-location-detector-probe method was found promising for locating defects along the length of the tube. Results of the probalog, dye-penetrant, and ultrasonic tests proved inconclusive in determining leak locations. (B.O.G.)
Date: February 24, 1961
Partner: UNT Libraries Government Documents Department
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Analytical considerations for K-downcomer and bellows

Description: A free body diagram of the bellows will show the possibility of three forces -- one in each direction, three moments -- one in each plane, and the internal pressure. Any or all of these forces and moments may fluctuate due to variations in a driving force, e.g., separation of streamlines which creates slugging of flow through an elbow. Whereas the static equilibrium condition can be analyzed and stresses and strains computed, the dynamic condition cannot be approached without information on the magnitude, frequency and location of the exciting force. Having the latter, some evaluation of the stresses to be expected can be made. By combining strains (or stresses) due to the various forces and moments, the point of maximum stress can be located and the point of maximum stress fluctuation for the fatigue cycle-amplitude-range curve can be determined. Further consideration must be given to stress concentrations. With the complete analysis in mind, we must determine how some of these forces and moments effect the tests and delineate what can he expected from the tests. This report considers each force or moment by itself and studies its relationship to the tests.
Date: February 28, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation, 1960

Description: This report discusses benefits in an increase in the flow of water from the lower depths of the Grand Coulee Dam which was used to lower river temperature at HAPO. A net average daily reduction of over 1.2{degree}C resulted at HAPO with a peak of 2.7{degree}C. The Net Production gain from temperature change was 6910 MWD and the Cost of Control was: Grand Coulee Charges $3,120.00, and other (Estimated) 6,880.00 for a total of $10,00.00.
Date: February 15, 1961
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Atomic Energy Levels in Crystals

Description: Report discussing discrete energy levels observed within certain crystals which are due to perturbations of energy levels of the free ion by an electrostatic field arising from the crystal lattice. The analytic procedures for determining the field from the charge configuration are given, and the resulting fields are classified according to their symmetry. After a general survey of group-theoretical ideas, the applicable groups are analyzed in detail, and characters appropriate for both integral and half-integral angular momenta of the free ion are tabulated. Text includes tabulations, equations, and matrices using Wigner and Racah coefficients.
Date: February 24, 1961
Creator: Prather, John L.
Partner: UNT Libraries Government Documents Department
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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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The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961

Description: Abstract: 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 metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been 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 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.
Date: February 6, 1961
Creator: Elliott, Rodney 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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Chemical Processing Department Monthly Report: January 1961

Description: This report, from the Chemical Processing Department at HAPO for January 1961, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: February 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
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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The Design and Operation of Purex Process Pulse Columns

Description: Information on the development of pulse columns for the Purex Process is presented in order to indicate qualitutively the performance attainable with improved cartridge designs, and to show some of the factors involved in scaling up pilot plant results to full plant scale. The pulse columns were designed to produce separated uranium and plutonium products decontaminated by at least a factor of 10>s7/sup /om fission products, with average uranium and plutonium losses of less than 0.2% per column and an overall yield of at least 99% of each product. The five types of behavior observed in pulse columns as a function of throughout rate and pulsing conditions are described. The effects of increasing frequency and throughput rate on pulse column efficiency are shown. The different types of perforated plates and packings investigated for Purex service are discussed. Short cuts, indicated by Purex development studies, that may be taken to provide a suituble column design with a minimum of pilot plant development are described. (M.C.G.)
Date: February 17, 1961
Creator: Richardson, G. L.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE During FY 1960

Description: The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redssign of system components to utilize alteraate coolants such as nitrogen, air, and NaK. The use of kerosene to replace tetralin, where double containment is provided, is discussed. The physical properties are compared, and kerosene is shown to be free of the undesirable characteristics of tetralin. The fuelelement cleaning systsm was redesigned for steam washing, followed by a water rinse and vacuum drying. Hydrogen gas evolved during washing is oxidized with copper oxide to eliminate the possibility of a hydrogen-oxygen explosion if air should accidentally enter the vent system. The fuel element was changed from a seven- to a five-rod cluster to provide additional clearance in the channel. Element hardware was modified to provide an orifice location which will permit more precise flow calculations; a redesigned hanger assembly which will minimize sodium holdup; and filter screene at the channel entrance to prevent in-cluster plugging. Diagnostic instrumentation was provided for the reactor to monitor: fission-product activity in the reactor cover gas; rapidly varying reactor parameters during a reactor scram; internnl and aheath fuel temperatures; and fuinctions being performed whioh wiIl indicate the mode of operation. The data wiIl provide additionul information to the reactor operator, as well as provide a more comprehereive coverage for reaotor analysis. (auth)
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mixers in the 7th and 15th position from the rear. Fuel cores representing the full range of UT-2 voltage values (grain size converts to d-c voltage) of interest are segregated into three categories: a. Large grains. b. Variations of grain size in an individual core. c. Small grains. Each category will be subdivided into three groups, each covering a small range of values. After canning, the finished fuel elements will be assembled into twenty-seven (27) charges in three latin square patterns for irradiation to a 900 MWD/T exposure goal in D Reactor.
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Turbulent Intensity and Geometry with Special Application to Axisymmetric Flow

Description: A relationship is derived between the mean square fluctuating current of a hot wire anemometer and the six turbulent Reynolds' stresses in the stream- coordinate system without employing the usual low turbulent intensity approximation. The relatively simple result is a consequence of assuming proportionality between the wire current reading and the perpendicular velocity component instead of the nonlinear dependence required by King's law. The assumption is valid for instruments equipped with the proper linearizing circuitry. Tbe stream-coordinate Reynolds' stresses are then related to the cylindrical polar Reynolds' stresses. An error analysis on the experimental determination of ore of these stresses is indicated but cannot be evaluated without fu rther data. (auth)
Date: February 21, 1961
Creator: Wichner, R. P. & Peebles, F. N.
Partner: UNT Libraries Government Documents Department
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Development of container materials for LAMPRE applications

Description: Some 53 high-purity binary tantalum-base alloys were prepared and evaluated as candidate materials of construc tion for the Los Alamos Molten Plutonium Reactor Experiment. Preliminary data indicate that good resistance to attack by the fuels can be obtained by alloying tantalum. Alloys containing additions of rhenium and tungsten showed good corrosion resistance in polythermal (1352 to 1022 deg F) tilting-furnace exposures. Tantalum--yttrium alloys also displayed good corrosion resistance, even though the yttrium apparently was lost during arc melting. Most of the alloys, including those which showed good corrosion resistance, were amenable to arc melting and casting and fabrication at room temperature. (auth)
Date: February 14, 1961
Creator: Drennen, D. C.; Langston, M. E.; Slunder, C. J.; Dunleavy, J. G. & Hall, A. M.
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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