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Cost Function Studies for Power Reactors

Description: A function to evaluate the cost of electricity produced by a nuclear power reactor was developed. The basic equation, revenue = capital charges + profit + operating expenses, was expanded in terms of various cost parameters to enable analysis of multiregion nuclear reactors with uranium and/or plutonium for fuel. A corresponding IBM 704 computer program, which will compute either the price of electricity or the value of plutonium, is presented in detail. (auth)
Date: November 1, 1961
Creator: Heestand, J. & Wos, L.T.
Partner: UNT Libraries Government Documents Department
open access

Investigation of joining techniques for advanced austenitic alloys

Description: Modified Alloys 316 and 800H, designed for high temperature service, have been developed at Oak Ridge National Laboratory. Assessment of the weldability of the advanced austenitic alloys has been conducted at the University of Tennessee. Four aspects of weldability of the advanced austenitic alloys were included in the investigation.
Date: May 1, 1991
Creator: Lundin, C. D.; Qiao, C. Y. P.; Kikuchi, Y.; Shi, C. & Gill, T. P. S.
Partner: UNT Libraries Government Documents Department
open access

KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS

Description: The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program uti… more
Date: February 1, 1962
Creator: Dunenfeld, M. comp.
Partner: UNT Libraries Government Documents Department
open access

Interpretation of a dipole-dipole electrical resistivity survey, Colado geothermal area, Pershing County, Nevada

Description: An electrical resistivity survey in the Colado geothermal area, Pershing County, Nevada has defined areas of low resistivity on each of five lines surveyed. Some of these areas appear to be fault controlled. Thermal fluids encountered in several drill holes support the assumption that the hot fluids may be associated with areas of low resistivity. The evidence of faulting as interpreted from modeling of the observed resistivity data is therefore particularly significant since these structures m… more
Date: September 1, 1980
Creator: Mackelprang, C.E.
Partner: UNT Libraries Government Documents Department
open access

An analysis of residential energy consumption in a temperate climate

Description: Electrical energy consumption data have been recorded for several hundred submetered residential structures in Middle Tennessee. All houses were constructed with a common energy package.'' Specifically, daily cooling usage data have been collected for 130 houses for the 1985 and 1986 cooling seasons, and monthly heating usage data for 186 houses have been recorded by occupant participation over a seven-year period. Cooling data have been analyzed using an SPSSx multiple regression analysis and … more
Date: June 1, 1987
Creator: Clark, Y.Y. & Vincent, W.
Partner: UNT Libraries Government Documents Department
open access

CONCEPTUAL DESIGN AND ECONOMIC EVALUATION OF A STEAM-COOLED FAST BREEDER REACTOR

Description: A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estim… more
Date: November 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Partner: UNT Libraries Government Documents Department
open access

California solar data manual

Description: Factors that determined the data contents of the manual are presented. Estimates of errors in the data are provided, and the impact of these errors on solar design is discussed. The state is divided into 15 solar zones of roughly similar solar radiation conditions, which are illustrated along with page references to the most relevant solar and climate data. A guide to the data tables and graphs is provided, which are displayed under solar, climate, and sky charts. A guide is given to simplified… more
Date: January 1, 1978
Creator: Berdahl, P.; Grether, D.; Martin, M. & Wahlig, M.
Partner: UNT Libraries Government Documents Department
open access

Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents. (ZPR-III Assembly 36)

Description: Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a … more
Date: January 1962
Creator: Gasidlo, J. M.; Long, J. K. & McVean, R. L.
Partner: UNT Libraries Government Documents Department
open access

Data Telemetry Package Powered by Strontium-90 Fueled Generator. Final Report

Description: An automatic, nuclear powered, meteorological data transmitting radio station was designed and fabricated for unattended service at a remote Arctic location. The system automatically measures air temperature, barometric pressure, wind direction, and two wind speed averages- Once every three hours it transmits this data in binary digital form, on two frequencies, to a manned receiving station (also designed as a part of this contract) where it is recorded on a two-channel recorder. Temperature, … more
Date: September 1, 1961
Partner: UNT Libraries Government Documents Department
open access

An analysis of residential energy consumption in a temperate climate

Description: Electrical energy consumption data have been recorded for several hundred submetered residential structures in Middle Tennessee. All houses were constructed with a common energy package.'' Specifically, daily cooling usage data have been collected for 130 houses for the 1985 and 1986 cooling seasons, and monthly heating usage data for 186 houses have been recorded by occupant participation over a seven-year period. Cooling data have been analyzed using an SPSSx multiple regression analysis and … more
Date: June 1, 1987
Creator: Clark, Y.Y. & Vincent, W.
Partner: UNT Libraries Government Documents Department
open access

REACTOR LABORATORY EXPERIMENTS

Description: An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-two experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment. (J.R.D.)
Date: August 1, 1961
Creator: Sturm, W.J. ed.
Partner: UNT Libraries Government Documents Department
open access

VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR

Description: Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron mult… more
Date: November 15, 1961
Creator: Cheverton, R.D.
Partner: UNT Libraries Government Documents Department
open access

FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Partner: UNT Libraries Government Documents Department
open access

An Out-of-Pile Electron Irradiation Circulating Loop for Fouling Studies

Description: An out-of-pile electron irradiation circulating loop was developed to study the problem of fuel element fouling in organic cooled reactors. Unlike pyrolytic loops and capsules, the irradiation loop operates at temperatures, pressures, fluid dynamics, geometry, and radiation damage which closely resemble reactor conditions. The loop is run in conjunction with the 4-kw -- 6-Mev electron linear accelerator. The thickness of the fouling film deposited in the irradiation cell is measured and the fil… more
Date: August 1, 1962
Creator: Mengelkamp, R. A.; Hudson, P. S. & Hillyer, J. C.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs

Description: A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods… more
Date: January 30, 1961
Partner: UNT Libraries Government Documents Department
open access

Preliminary Hazards Summary Report on the Brookhaven High Flux Beam Research Reactor

Description: The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 10/sup 15/cm/sup -2/ sec/sup -1/ and a flector thermal maximum flux of 7 X 10/sup 14/ cm/sup -2/ sec/sup -1/, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and… more
Date: May 1, 1961
Creator: Hendrie, J. M. & Kouts, H. J. C.
Partner: UNT Libraries Government Documents Department
open access

Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Description: Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging f… more
Date: March 1, 1962
Creator: Gibson, G. W. & Shupe, O. K.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor

Description: A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Th… more
Date: August 29, 1962
Partner: UNT Libraries Government Documents Department
open access

Irradiation Behavior of Restrained and Vented Uranium-2 w/o Zirconium Alloy. Final Report-Programs 6.1.22 and 6.1.27

Description: Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded… more
Date: June 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Yaggee, F. L.
Partner: UNT Libraries Government Documents Department
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