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Paper Presented by M. Minashin

Description: The attached paper is a translation of a rough draft of the paper, "Operating Experience of the APS-1", presented by M. Minashin in Russian at the IAEA Conference on Small and Medium Power Reactors, Vienna, Austria, September 5-9, 1960.
Date: November 1, 1960
Creator: Ullmann, J. W. & Gerrrard, Martha
Partner: UNT Libraries Government Documents Department
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Local Reactivity "Worth" in the HRT

Description: The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date: October 11, 1960
Creator: Jaye, S. & Vondy, D. R.
Partner: UNT Libraries Government Documents Department
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EXPIRE - A Reactivity Lifetime Calculation

Description: EXPIRE is a calculation which predicts the reactivity-lifetime, instantaneous and integrated effective multiplication constants and instantaneous and integrated effective multiplication constants and instantaneous conversion ratio for heterogeneous reactors. The concentration of all the isotopes of interest from Th232 to Am243 are calculated as a function of time using the average reactor power density and a uniform flux distribution. The equations have been programmed for the IBM-704 computer … more
Date: October 13, 1960
Creator: Jaye, S.
Partner: UNT Libraries Government Documents Department
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Estimation of Reaction and Heat Release Rates for Graphite Oxidation

Description: A literature study has been made of rates for the reaction of oxygen with high-purity artificial graphite. Values from a number of sources have been expressed on a common basis which provides approximate correction for the retarding effects of oxygen diffusion in the graphite pores. The corrected rates can be correlated by the equation k = 7.24 x 10^9 exp (-22 100/T), where k has units of weight fraction oxidized per hour and T as in °K. Effects of oxygen concentration, solid and gas-phase cont… more
Date: October 19, 1960
Creator: Prados, John W.
Partner: UNT Libraries Government Documents Department
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A Study of Uranium Isotopic Ratio Information from the HRT

Description: Samples taken at low power ("no loss" conditions ) over a period from Run 12 to Run 21 were analyzes by mass spectrograph to determine uranium isotopic composition. Results conformed that part of the uranium inventory is at all times held up, out of solution, in the reactor and that there is limited isotopic exchange between dissolved uranium and uranium in solids.
Date: unknown
Creator: Piper, H. B.; Buxton, S. R. & Haubenreich, P. N.
Partner: UNT Libraries Government Documents Department
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Dry Maintenance Facility for the HRT

Description: A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date: October 11, 1960
Creator: Holz, P. P.
Partner: UNT Libraries Government Documents Department
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Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment

Description: The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date: May 8, 1961
Creator: Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
Partner: UNT Libraries Government Documents Department
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Electrical Design Standards and Graphical Symbols

Description: This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date, and supersedes the previously issued ORNL Electrical Symbols List and CF-58-12-141, Electrical and Electronic Drawing Standards for Wiring and Device Coding and Applications.
Date: October 1960
Creator: Bates, A.E.G; Bowelle, M.M.; Horton, J. L.; Moore, R. L.; Hyland, R. F. & Brashear, C.
Partner: UNT Libraries Government Documents Department
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Electrical and Electronic Symbols & Drawing Committee

Description: This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain e… more
Date: November 1961
Creator: Bates, A.E.G
Partner: UNT Libraries Government Documents Department
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Decontamination of EGCR Charge and Service Machines

Description: Methods for the noncorrosive removal of volatile fission products and UO2 dust from carbon steel and stainless steel have been developed. Procedures for applying these methods to the decontamination of the EGCR charge and service machines are described.
Date: October 13, 1960
Creator: Meservey, A. B.; Chilton, J. M. & Ferguson, D. E.
Partner: UNT Libraries Government Documents Department
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Removal of Strontium from Wastes

Description: The hazard of Sr^90 arises in part from its fixation by phosphates in the skeletal system. It is natural then to consider compounds and minerals associated with the phosphate anion for applications in waste disposal. Calcium phosphate floc formation is widely used as a method for removing strontium from contaminated water. Also, calcerous soils are said to be effective for removing strontium from low-level wasters containing dissolved phosphates. It is suggested that one the mechanisms involved… more
Date: November 28, 1960
Creator: Tamura, T. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Determination of Free Acid in Highly Radioactive Solutions by Remotely Controlled Conductometric Titration

Description: A conductometric titration method described by Goldstein was adapted for use in a remote analytical facility. The results obtained by mean of experiments made prior to this adaptation indicated that methanol is the most satisfactory medium in which to determine excess sulfuric acid in uranyl sulfate solutions that stimulate Homogeneous Reactor type fuel. When methanol is used, the complexation of hydrolyzable ions with sodium fluoride, as described by Pepkowitz, Sabol, and Dustin, is not requir… more
Date: October 13, 1960
Creator: Corcoran*, R. E.; Zittel, H. E.; Dinsmore, S. R. & Koskela, U.
Partner: UNT Libraries Government Documents Department
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Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab

Description: A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy dis… more
Date: October 26, 1960
Creator: Aulender, S. & Trubey, D. K.
Partner: UNT Libraries Government Documents Department
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Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials

Description: Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date: December 5, 1960
Creator: Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Statue of Pilot Plant Section Equipment Development Program

Description: A development program is being carried out in the pilot plant to improve the equipment involved in monitoring, metering and pumping process streams. The equipment under development includes an alpha monitor, a gamma monitor, a waste water monitor, a liquid flow rate meter, a canned rotor pump, a diaphragm pump, air lifts and a pressure tank pump. This report presents the present status of the testing program.
Date: October 14, 1960
Creator: Mackey, T. S.
Partner: UNT Libraries Government Documents Department
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The Helium Purification System for the Proposed Pebble Bed Reactor Experiment

Description: A helium coolant side-stream purification system consisting of parallel sections for radioactive and non-radioactive de-contamination was designed for the proposed Pebble Bed Reactor Experiment. Primary equipment components are two gas coolers, gas heater, charcoal delay trap, CuO oxidizer, Molecular Sieve adsorber, and full flow filter. The charcoal delay trap is sized to provide a hold-up of 30 minutes for Kr isotopes, 6hr hold-up for Xe isotopes, and 99.9% retention of iodine isotopes result… more
Date: October 25, 1960
Creator: Scott, C. D.; Finney, B. C. & Suddath, J. C.
Partner: UNT Libraries Government Documents Department
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Synthesis of Dimethyl Selenide

Description: The preparation of essentially pure dimethyl selenide for the Isotype Separations Group, Chemistry Division, is described. The compound was prepared by warming a mixture of selenium, sodium hydroxide, sodium formaldehyde sulfoxylate in aqueous solution for several hours at 50°C and then adding methyl iodide. Dimethyl selenide was removed by distillation.
Date: October 7, 1960
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Description of the Ibm-704 Code for the Calculation of Concentration Transients in the HRT

Description: The calculation of concentration transients caused by mixing in the interconnected three-body system of the fuel dump tanks, core and blanket has been coded for the IBM-704. The system of equations includes material balances, the dependence of critical temperature on core and blanket concentrations, and the effect of temperature (density) changes on flow rates. The controllable flow rates, the fuel dump tank weight and the initial conditions are input variables. Outputs include core and blanket… more
Date: October 4, 1960
Creator: Piper, H. B. & Haubenreich, P. N.
Partner: UNT Libraries Government Documents Department
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HFIR Reactor Vessel Expansion Problems

Description: The attached memo by G. N. Krouse of Sturm-Krouse, Inc. gives results of a preliminary analysis of the deflections of beam holes due to thermal expansion and internal pressure in the vessel. A partial solution of the problem is suggested. Based on preliminary pressure-temperature data the following deflections were derived: Movement of horizontal beam tubes = 0.046 in. Movement of Engineering facility tubes = 0.117 in. Vertical motion of the vessel at the horizontal beam tubes due to thermal ex… more
Date: October 3, 1960
Creator: Gall, W. R.
Partner: UNT Libraries Government Documents Department
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Fundamental Studies in Heat Transfer and Fluid Mechanics, Status Report July 1, 1959- Feb 29, 1960

Description: Experimental determination of heat-transfer coefficients, burnout heat fluxes, and friction factors have been made for swirl flow of low-and moderate-pressure water through electrically heated aluminum, nickel, and copper tubes containing full-length Inconel twisted tapes. For nonboiling conditions, swirl-flow heat-transfer coefficient were successfully correlated with both the Froude modulus (the ratio of inertial to centrifugal forces) and a grouping of the Grashof and Reynolds moduli (ratio … more
Date: October 4, 1960
Creator: Hoffman, H. W.; Gambill, W. R.; Keyes, J. J., Jr. & Kidd, G. J., Jr.
Partner: UNT Libraries Government Documents Department
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Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source

Description: The solution of the monoenergetic Boltzmann equation in an infinite homogeneous, nonmultiplying medium with linearly anisotropic scattering and an isotropic plane source is given and compared with the corresponding solution for isotropic scattering. The effective source strength for the asymptotic flux turns out to be the same as that for isotropic scattering to first order in Σa/Σ.
Date: September 6, 1960
Creator: Inonu, Erdal
Partner: UNT Libraries Government Documents Department
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Progress Report for August-September 1960

Description: A chemical flowsheet is proposed for recovery of strontium and rare earths from Purex wastes. The iron in the waste is first complexed with tartrate and the pH is adjusted with caustic. Strontium and rare earths are extracted by a solvent comprised of di(2-ethylhexyl)phosphoric--sodium di (2-ethylhexyl) phosphate--tributyl phosphate -- Amsco 125-82. and are stripped with nitric acid. Processing the strip product through additional solvent extraction cycles yields isolated, concentrated strontiu… more
Date: December 29, 1960
Creator: Brown, K. B.
Partner: UNT Libraries Government Documents Department
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Preliminary Analog Computer Study of the Small EGCR In-Pile Loops

Description: The ORNL analog computer was used to simulate four widely different experiment conditions in the small EGCR in-pile loops. Various control and safety systems were evaluated in each case. Curves are included which show the response to postulated accidents and component failures. The results indicate that one standard control and safety system will probably be adequate for a wide variety of test conditions.
Date: September 21, 1960
Creator: Ball, S. J. & Beasley, E. G.
Partner: UNT Libraries Government Documents Department
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