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AETR NUCLEAR MOCKUP DESIGN

Description: The Advanced Engineering Test Reactor (AETR) nuclear mockup is designed to be a flexible, inexpensive developmental facility which duplicates the reactor portion of the AETR and which would be used to verify the operation of reactor controls. The mockup would also furnish measurements of temperature and void coefficients, flux shapes, and critical mass, and facilitate a reliable AETR design in a minimum time, and with minimum development cost. For even greater usefulness, the mockup is also designed for use in conjunction with an operating AETR to check the reactivity of experiments and fuel assemblies, and for other annular core reactor development purposes. In these respects, the mockup design embodies the concepts for a very low power nuclear auxiliary outlined in an earlier report. Detail design was limited to the reactor assembly and control systems and it is assumed that a simple building with supporting facilities may be readily supplied by private industry or the AEC. Results of negotiations with potential vendors and fabricators, a description of the facility components, and design drawings suitable for contractor use are presented. Preliminary quotations from fabricators and suppliers indicate that the facility can be in operation within an eight month period at a total cost not exceeding
Date: October 1, 1959
Creator: Leonard, B.H.; Bertelson, P.C.; Kornfeld, M.J. & Wade, E.E.
Partner: UNT Libraries Government Documents Department
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The bumpy torus

Description: "In this paper the single particle motion in the magnetic field created by a circular array of circular current loops is investigated." (p. 3)
Date: October 1959
Creator: Gibson, Gordon; Jordan, Willard C. & Lauer, Eugene J.
Partner: UNT Libraries Government Documents Department
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COHERENT RADIATION FROM A PLASMA

Description: The so-called Collisionless Boltzmann Equation'' or Vlasov Equation'' has been derived previously by Harris by use of a complete statistical treatment of both the plasma particles and the electromagnetic fields. It is shown that a consequence of this approximation is that the entropy of the electromagnetic field as well as that of the plasma particles is a constant. This result is used to demonstrate that only completely the Vlasov equation. (auth)
Date: October 1, 1959
Creator: Harris, E.G. & Simon, A.
Partner: UNT Libraries Government Documents Department
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The Determination of Chlorine in Polyurethane Plastic

Description: Chlorine may be determined in polyurethane by gravimetric or spectrophotometric techniques. The sample is burned in a special combustion tube with two oxygen inlets, the products of combustion are absorbed in a solution containing sodium hydroxide and hydrogen peroxide, and the chlorine is measured either gravimetrically as silver chloride or spectrophotometrically using mercuric thiocyanate and ferric perchlorate. Eighteen determinations of cblorine in known solutions of sodium chloroacetate or perchloric acid gave an average recovery of 98.3% with a standard deviation of 2.8%. (auth)
Date: October 1, 1959
Creator: Henicksman, A. L.; VanKooten, E. H.; Gardner, R. D. & Ashley, W. H.
Partner: UNT Libraries Government Documents Department
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Examination of Jacketed Uranium Slugs from the Los Alamos Fast Reactor "Clementine"

Description: Examination of clad uranium reflector slugs wbich falled by rupture and swelling during the first year of operation of Clementine revealed no anisotropic damage to the uranium because of burnup or thermal cycling. The cladding was found to be of high-sulfur-free-machining steel, and it is postulated that thermal stresses caused welding flaws to open enough to permit seepage and corrosive attack upon the uranium cores by the reactor coolant (mercury). (auth)
Date: October 1, 1959
Creator: Paine, S. H.; Murphy, W. F. & Brown, F. L.
Partner: UNT Libraries Government Documents Department
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FLUID-BED CONVERSION OF URANIUM TETRAFLUORIDE TO URANIUM HEXAFLUORIDE

Description: Experiments conducted in a 2 1/2-inch diameter reactor have demonstrated that the continuous fluorination of uranium tetrafluoride to hexafluoride with elemental fluorine in a fluidized bed is possible. Practicable fluorine efficiencies and conversion rates were attained with good temperature control in experiments with refined uranium tetrafluoride. Runs made with crude uranium tetrafluoride, derived from the reduction and hydrofluorination of ore concentrates produced by the acid-leach process, indicated that these also can be processed at satisfactory ratss and efficiencies. Uranium tetrafluoride derived from carbonate-leached ore concentrate gave a lower production rate and was more difficult to process because of sintering tendencies. (auth)
Date: October 1, 1959
Creator: Vogel, C.J. & Mecham, W.J.
Partner: UNT Libraries Government Documents Department
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FUEL DEFECT TEST-BORAX-IV

Description: On March 11 and 12, 1958, the BORAX-IV reactor was operated at a power of 2.4 Mw, even though a large number of the fuel elements contained defects through the cladding. Subsequent investigation showed that 22 of the fuel elements in the reactor contained one or more ruptured rods. During operation, radiation fields in the vicinity of the turbine and condenser were high, but on shutdown all radiation levels decayed rapidly with a 30-min half life and after 12 hr all parts of the turbine and condenser showed only normal radiation levels of a few mr/hr. The effluent gases, the reactor steam, the condensate, and the reactor water were sampled during steady operation and analyzed for fission product gases and other fission products. An analysis of the data was made using information obtained from tests of defect ceramic fuel in EBWR, and an attempt was made to predict contamination levels throughout the system. Predicted levels agreed qualitatively with those found and in general the method led to high results. On the basis of these experiments it can be predicted that a boiling reactor, fueled with ceramic fuel, can operate for long periods of time with many defects through the cladding. Under these conditions, although activity levels may be hlgh during operation, no significant amount of long-lived contamination, other than fission gases which have stable daughters, will be released to the reactor surroundings. (auth)
Date: October 1, 1959
Creator: Robertson, R. F. S. & Hall, V. C., Jr.
Partner: UNT Libraries Government Documents Department
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GENERAL REACTOR ANALYSIS COMPUTER PROGRAM FOR THE IBM 704, PROGRAM GEORGE

Description: Program George is an IBM 704 ccde that combines standard ANPD reactor analysis methcds for computing multiplication constant and spatial distribution of flux and power, as well as other nuclear parameters, in aircraft (heterogeneous) reactors. The elapsed time and the chance for human error between initial input and final output are greatly reduced in Program George. A matched set of reflector savings for a reflected, cylindrical core, which was formerly obtained by hand, is now computed by the program. In the C/sub 2/ pcrtion of Program George, the ccde computes the neutron slowingdown density and flux at 19 lethargy levels plus a thermal group in bare, homogeneous compositions with normal mode, ene ngy-dependent bucklings. The diffusion coefficient contains a transport correction as well as a Behrens correction for heterogeneous structure. Flux-depression factors at thermal and two epithermal levels are computed in annular, cylindrical geometry by one-energy, P/sub 3/ transport theory approximation in the I/sub 2/ pontion of the program, or they may be given as input. Flux weighting of various cross sections, transmission factors, and other parameters are computed in a multigroup representation. Two-energy-group constants from the regional compositions are supplied in the F/sub 2/ portion of the program, in which a two-energy group, one-space-dimensional, multiregion diffusion calculation yields multiplication constant, normalized fission density, fast flux, and slow flux in each onedimensional reactor pontrayed. If a reactivity match is requested, the reflector savings of the specified compositions are adjusted until the multiplication constant i n the radial F/sub 2/, longitudinal F/sub 2/, and the reference bare equivalent core of a cylindrical reflected reactor converge to the same value. (auth)
Date: October 1, 1959
Creator: Hoffman, T.A. & Henderson, W.B.
Partner: UNT Libraries Government Documents Department
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Geology of the Marble Exploration Hole 4, Nevada Test Site, Nye County, Nevada

Description: From introduction: This report summarizes the information obtained during preparation of the lithologic log of the core and presents results of chemical analyses of marble samples collected from surface near the drill hole. The report was prepared by the U.S. Geological Survey on behalf of the Albuquerque Operations Office, U.S. Atomic Energy Commission.
Date: October 1959
Creator: McKeown, F. A. & Wilmarth, V. R.
Partner: UNT Libraries Government Documents Department

[Herman Clark handing gifts]

Description: Photograph of Herman Clark handing wrapped gifts to an unidentified woman. She is holding gifts on one hand while holding a cowbell with the other. They look at each other and appear to be speaking.
Date: October 1, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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High-Flux Heat Transfer Studies: An Analytical Investigation of Laminar Film Boiling

Description: An analysis was made of siable, laminar, free convection, film boiling from isothermal vertical plates and horizontal cylinders surrounded by a saturated liquid, where radiation was only of minor importance. The mathematical techniques of boundary layer theory were used and the boundary layer equations were reduced to ordinary differential equations by means of a transformation similar to those used in free convection and condensation. The equations were solved for: (1) compressible flow with variable specific heat, (2) variable specific heat and density variations considered only in the evaluation of the buoyant force, and (3) the case of constant properties. Numerical results were obtained for: (1) near critical water at 2800 and 3100 psia with wall to liquid temperature differences of 250, 500, and 1000 deg F; (2) for fluids with Prandtl numbers of 2/3, 1, and 2; and (3) for mercury and methanol film boiling at one atmosphere, considering constant properties. The results obtained by assuming constant properties were compared to: (1) the results obtained by considering variable properties, (2) experimental results, and (3) the comparable case of laminar film condensation. It was shown that the method of considering density variations only in the evaluation of the buoyant force is not valid in film boiling. It was also shown that the constantproperty solutions for heat transfer did not always agree with solutions obtained considering compressible flow and variable specific heat. An approximate analysis of a nonisothermal wall, including the effects of radiation, was presented. It was shown that for high emissivity walls at high temperature, radiation is the controlling factor in film boiling heat transfer. (auth)
Date: October 1, 1959
Creator: McFadden, P. W. & Grosh, R. J.
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Density Gauge. Quarterly Report No. 1 Covering the Period From June 1 to September 1, 1959

Description: A mass gaging technique is being investigated in which the detector alternately views radiations transmitted through the test specimen and through a calibrated step wedge. Thulium-170 was used in initial investigations; however, sources of higher and lower energies are to be examined. Variations of balancing systmas are discussed and results of tests using NaI(Tl) and CsI(Tl) crystals with non-commutating systems are tabulated. Commutating system's operation was tested at a chopping frequency of 10 cps. Much smoother servo operation was noted than was demonstrated by the non-commutating system. A circuit diagram of the commutating system is included. (J.R.D.)
Date: October 1, 1959
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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Ion-Molecule Reactions

Description: Introduction: The present report is a critical review of the present knowledge and theory of ion-molecule reactions, especially as they may apply to high-level radiation processing.
Date: October 1959
Creator: Rosenstock, H. M.; Mueller, C. R.; Wallenstein, M. B.; Vestal, Marvin L.; Tory, Audrey; Rivers, Diana et al.
Partner: UNT Libraries Government Documents Department
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IRRADIATION OF EXTRUSION-CLAD URANIUM-2 w/o ZIRCONIUM ALLOY FOR EBR-I, MARK III

Description: ABS>The fuel material specified for the Mark III core of EBR-I was uranium-2 wt. % zirconium alloy coextruded with Zircaloy-2 cladding. From previous work on swaged or rolled uranium-2 wt% zirconium alloy, it was anticipated that the extruded alloy would be dimensionally unstable under irradiation unless stabilized by suitable heat treatment. In order to determine an effective heat treatment, irradiation studies were made on both clad and unclad extruded uranium-2 wt.% zirconium alloy specimens at irradiation temperature estimated at 200 to 750 deg C. The irradiation specimens included material with three different heat treatinents, selected on the basis of previous studies, and material transient melted in its cladding. For unclad specimens, it was found that the irradiation temperature strongly influenced the various irradiation growth rates resulting from different heat treatments. Growth rates of the clad specimens were relatively insensitive to either irradiation temperature or prior heat treatment An exception was the transient-melted material, which shortened under irradiation. The cladding had only limited ability to restrain the swelling rates of specimens irradiated at the more elevated temperatures. Clad transient-melted material was found to be most resistant to high-temperature swelling under irradiation. The results of the present study combined with observations in earlier investigations resulted in a recommendation that the reference heat treatment for the core consist of gamma solution at 800 deg C followed by isothermal transformation at 690 deg C. (auth)
Date: October 1, 1959
Creator: Kittel, J.H.
Partner: UNT Libraries Government Documents Department

[Larry Morrell with a ballot box]

Description: Photograph of Larry Morrell putting a piece of paper into a ballot box. He is standing to the right of a Gordon Boswell Flowers sign. He wears a suit and tie. Morrell looks directly at the camera and smiles.
Date: October 1, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[Larry Morrell with flowers]

Description: Photograph of Larry Morrell holding a bouquet of flowers in front of a Gordon Boswell Flowers sign. He wears a suit and tie. Morrell looks directly at the camera and smiles.
Date: October 1, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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LECTURE NOTES ON HEAT EXTRACTION FROM BOILING WATER POWER REACTORS

Description: Calculation procedures for the thermal ard hydraulic performance of boiling reactors are outlined relative to boiling heat transfer, evaporator- condenser heat transfer, fuel element heat transfer, and steam heat transfer equations. Various engineering systems for evaluating the twophase pressure drop are given; the corrected MartinelliNelson method was found most adequate. Working curves for calculating velocity ratios and steam volume fractions are given which are accurate to within plus or minus 15%. Expressions are given for calculating pool ard film boiling and net and local boiling burnout for various geometrical arrangements. Calculation procedures are given for natural and forced circulation system analysis and compared to experimental data. Design criteria are discussed with calculation procedure given for the design parameters: moderafor to fuel ratio, critical maximum heat flux, vapor-liquid separation, and reactor geometry, natural vs. forced circulation. The calculation procedure is illustrated by a sample core analysis. The physical and thermodynamic properties of light and heavy water are given. (C.J.G.)
Date: October 1, 1959
Creator: Lottes, P.A.; Petrick, M. & Marchaterre, J.F.
Partner: UNT Libraries Government Documents Department

[Man resting his hand on Johnny Sullivan's shoulder]

Description: Photograph of Johnny Sullivan and an unidentified man at a party. Sullivan is wearing a vertical striped blazer and is holding a cowbell and an envelope, which he is looking at. The other man has his left hand on Sullivan's shoulder and is looking off to the right of the image and smiling. They are standing behind a table that has stacked cups and a plant on it.
Date: October 1, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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A Method of Calculating Boundary-Layer Thickness in Axisymmetric Nozzles with Laminar Hypersonic Flow

Description: Abstract: "The excellent agreement between measured boundary layer thickness and thickness calculated by Sivells and Payne recommends their method for calculating turbulent boundary layer growth in axisymmetric hypersonic nozzles. It was thought worthwhile to adapt their approach to the laminar boundary layer. This analysis, along with a limited amount of corroborating data, is presented herein."
Date: October 1959
Creator: Johnson, Arlo F.
Partner: UNT Libraries Government Documents Department
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