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Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Item Type: Refine your search to only Report
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Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Item Type: Refine your search to only Report
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Preprocessing of Procedure in the ORACLE-Algol Translator

Description: This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on th… more
Date: May 15, 1961
Creator: Bumgarner, L. L.
Item Type: Refine your search to only Report
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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 included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, com… more
Date: February 2, 1961
Creator: Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Item Type: Refine your search to only Report
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Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow

Description: A relationship is derived the mean square fluctuating current of a hot wire anemometer and the sic 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 non-linear dependence required by King's law. The assumption is valid for instruments equipped with the proper… more
Date: February 21, 1961
Creator: Wichner, R. P. & Peebles, F. N.
Item Type: Refine your search to only Report
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HFIR Beryllium Reflector Preliminary Design Report

Description: This report considers the HFIR reflector design criteria and presents a summary of the reflector design. The reflector type chosen as complying best with the established criteria consists of a 3 in. thick removable beryllium annulus utilizing four concentric cylinders with cooling water flowing through the annuli between cylinders, and an outer 9 in. thick permanent beryllium annulus with axial circular coolant holes. Reflector support structures and experimental facilities are described and pr… more
Date: February 21, 1961
Creator: Hilvety, Neil
Item Type: Refine your search to only Report
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Apparent Observations Ionic Sound Waves in an Arc Plasma

Description: Oscillations have been observed in a magnetically supported cylindrical rod of plasma. This rod of plasma can be the discharge occurring in the defining aperture of a Mode II, pressure gradient arc. Similar oscillations can also occur in the column of a Mode I arc. These oscillations appear to be the mechanism that drives the Mode II blowup phenomena.
Date: February 13, 1961
Creator: Alexeff, I. & Neidigh, R. V.
Item Type: Refine your search to only Report
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Fuel-Cycle Analysis and Proposed Fuel and Burnable Poison Distribution and Loading for the HFIR and HFCE-2

Description: Further calculations have been made to determine the desired radial fuel distribution in the HFIR and in the forthcoming HFIR critical experiment. In the process the design of the core was changed to include a 1-cm-thick annular space of water between the two nearly equally thick fuel annuli, a metal-to-water ratio in the fuel annuli of 1.0 (0.050 in. thick plates and coolant channels ) was specified, and the active length of the core was increased from 18 to 20 in. Results of the calculations … more
Date: February 2, 1961
Creator: Cheverton, R. D.
Item Type: Refine your search to only Report
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Thermal Cycling Test of 3 1/2-in. and 4-in. Freeze Flanges

Description: A total of 104 thermal cycles between 250°F and 1350°F were imposed on a 3 1/2-in. and a 4-in. freeze flange to determine their susceptibility to thermal fatigue. The flange clamping arrangement was modified and various gaskets were used during the cycling in an effort to reduce the gas leakage problem.
Date: February 2, 1961
Creator: Moyers, J. C.
Item Type: Refine your search to only Report
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Generalized Heat Conduction Code for the IBM-7090 Computer

Description: The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be p… more
Date: February 9, 1961
Creator: Fowler, T. B.
Item Type: Refine your search to only Report
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Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves

Description: Equilibrium krypton and xenon adsorption isotherms were obtained for four varieties of charcoal and for Linde Molecular Sieves Types 4A and 5A, generally at 0, 25, and 60°c. Such data are of interest in connection with design and evaluation of adsorbers for radioactive noble gas fission products. The isotherms were fitted, by linear regression analysis, to straight-line forms of the Freundlich and Langmuir equations. The Freundlich linear equation gave the better fit and the parameters of this … more
Date: February 14, 1961
Creator: Ackley, R. D. & Browning, W. E., Jr.
Item Type: Refine your search to only Report
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Processing of Beryllium Oxide Fuels

Description: Preliminary results from experiments on the dissolution of beryllium metal and sintered UO2-BeO fuel pellets are reported. In all cases the pellets were fired in hydrogen at 1650-1800°C. Uranium, from UO2-BeO pellets containing more than 60% UO2, is readily leached with boiling 6-13 M HNO3 in about 6 hr. The BeO in these pellets dissolves only slowly in nitric acid; however, in 8 M HNO3-0.2M NaF, it dissolves at about the same rate as the UO2. Sintered pellets containing less than 10% UO2 do no… more
Date: February 13, 1961
Creator: Warren, K. S. & Perris, L. M.
Item Type: Refine your search to only Report
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Chemical Development Section C Progress Report for December 1960 and January 1961

Description: Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nit… more
Date: June 2, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
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Multi-temperature Cross Section Tape for the GNU Multigroup Calculation

Description: A cross section tape has been prepared containing data for elements of most interest for aqueous homogeneous reactor multigroup diffusion calculations involving combinations of 150, 200, 240, 260, and 280°C temperatures. This tape permits multigroup analysis of a reactor in which two or more regions are at different temperatures.
Date: January 25, 1961
Creator: Vondy, D. R.
Item Type: Refine your search to only Report
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Multiple Controllers for a Single Process

Description: A multiple controller system for a single process is formulated in block diagram form. It is shown that for the general case of n controllers and one type of cross coupling, the system equations can be reduced to the standard forms of servomechanism theory. The effects of failure in individual controllers are examined, and it is demonstrated that the system shows considerable promise for both reliability and maintenance without process interruption.
Date: January 25, 1961
Creator: Weaver, C. H.
Item Type: Refine your search to only Report
open access

THOROBRED - An IBM-704 Code for Steady State Nuclear and Economic Calculations of Two=Region Homogeneous Reactors

Description: THOROBRED is an IBM-704 code for the calculation of nuclear and economic characteristics of two-region homogeneous reactors operating on a U-Th fuel cycle in the steady state. The major input variables are reactor dimensions, power level, thorium concentration, chemical and purification systems cycle times, corrosion rates, fraction of Pa loss, and nuclear and economic data. The output includes equilibrium isotope concentrations, neutron balance, and a breakdown of fuel cost. Running times are … more
Date: January 17, 1961
Creator: Jaye, S. & Fowler, T. B.
Item Type: Refine your search to only Report
open access

Pressure Vessel Exposure to Fast Neutrons

Description: In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pres… more
Date: January 21, 1960
Creator: Carlsmith, R. S.
Item Type: Refine your search to only Report
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Xenon and Samarium Poisoning

Description: The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date: January 23, 1961
Creator: Carlsmith, R. S.
Item Type: Refine your search to only Report
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A Useful Solution for Short Cylindrical Shells and Other Applications

Description: The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notatio… more
Date: February 14, 1961
Creator: Moore, S. E.
Item Type: Refine your search to only Report
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Sources and Availability of Helium

Description: A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date: January 19, 1961
Creator: Fraas, A. P.
Item Type: Refine your search to only Report
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Revised Version of HFIR Critical Experiment-2 (HFCE-2)

Description: A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date: January 16, 1961
Creator: Kasten, P. R. & Cheverton, R. D.
Item Type: Refine your search to only Report
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