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A Revision of Computer Code POWERCO (Cost of Electricity Produced by Nuclear Power Stations) to Include Breakdowns of Power Cost and Fixed Charge Rates

Description: Report that "describes a new version of the code, POWERC-50, which contains several changes" to the previous code, POWERCO-25, which was used to calculate "the levelized cost of electricity produced by nuclear power stations" (p. 1)
Date: August 1969
Creator: Salmon, Royes
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Graduate Programs for the Health Physicist in the United States

Description: The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these p… more
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C

Description: The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for … more
Date: August 11, 1964
Creator: Moore, J. P.; Fulkerson, W. & McElroy, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C

Description: The experimental details, mathematical models, and typical data for a rapid comparative method for thermal conductivity measurements are presented. The method consists of measuring the temperature change of a small silver sphere after it is brought in contact with a small disk-shaped specimen which was initially at ta higher temperature. This temperature change was calibrated in the range of 50 to 400 degrees C by making measurements on samples of know thermal conductivity. The accuracy of this… more
Date: August 11, 1964
Creator: Kollie, T. G.; McElroy, D. L.; Graves, R. S. & Fulkerson, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Properties of Grade CGB Graphite

Description: Grade CGB graphite is a nuclear graphite which is basically an extruded petroleum coke bonded with coal tar pitch. No carbon blacks are used and the low-permeation graphite is finished through a series of impregnations and heat treatments with a final heat treatment of all components to 2800 degrees C. A listing of the results obtained is given in Table 1. The results at 51 degrees C are considered questionable. There was a slight contamination of the 90% Pt 10% Rh-Pt thermocouples at 910 degre… more
Date: August 11, 1964
Creator: Moore, J. P. & Godfrey, T. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Deposition of Submicron-Size Particles in Ventilation Ducts

Description: The purpose of this study was to investigate mathematically the concentration decrease due to particle deposition phenomena in highly concentrated monodispersed aerosols (mean particle size less than 1.0 mu) flowing through ventilation ducts. It was found that, from the standpoint of removal, the decrease in concentration due to deposition on duct walls was insignificant; but, when considering contamination on duct walls, the amount deposited, even though small when compared with the amount in … more
Date: August 1964
Creator: Davis, L. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

Description: From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: August 1962
Creator: Pennington, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report for February-March 1961 - Chemical Development Section C, Chemical Technology Division

Description: This report summarizes certain activities by the Oak Ridge National Laboratory's Chemical Technology Division, which focused on chemical separation processes relevant to nuclear fuel reprocessing, from February to March 1961. It includes data from experiments exploring the recovery of thorium and uranium from granitic rock, fission product (cesium) recovery, final cycle plutonium recovery by amine extraction, and the separation of transplutoniums from lanthanides.
Date: August 15, 1961
Creator: Brown, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of Radial Neutron-Flux Distribution in EGCR Lattice Cell

Description: The Neutron-flux distributions in an EGCR cell containing seven rod clusters of 2.0 and 2.6% enriched uranium oxide have been obtained by using a one-velocity, one-dimensional P-3 solution to the neutron-transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experimental and calculated distributions. Flux traverses in the outer rod perpendicular to a diameter of the cluster are also presented.
Date: August 31, 1959
Creator: DeBoer, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Californium Production in the High Flux Isotope Reactor

Description: Californium-252 and other isotope production rates resulting from irradiating Pu-242 in the proposed High Flux Isotope Reactor were estimated. The effect of curium recycle was investigated and optimum irradiation cycles determined.
Date: August 31, 1959
Creator: Claiborne, H. C. & Lietzke, Marjorie P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of Effective Resonance Integrals

Description: Effective resonance integrals for fuel and fertile materials were calculated as a function of materials concentration in homogeneous media. For the fissile materials (U-235, Pu-239), results were obtained from multigroup, monte-carlo, and statistical model calculations. For the fertile materials (U-238), results were obtained from monte-carlo and multigroup calculations and were compared with experimental results.
Date: August 28, 1959
Creator: Jaye, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Flame Photometyry for the Determination of Elements of the Rare-Earth Group

Description: Flame spectra are presented of all rare-earth elements except cerium and promethium, and also of the closely related elements, scandium and yttrium. The precise wave length and relative spectral intensity of each line and band, as well as the band width of all bands, are tabulated. Also included in this tabulation are the relative spectral interferences of other elements of the group studied which interfere with the emissivity measurements of the bands and lines listed. Based on the spectra and… more
Date: August 27, 1959
Creator: Menis, Oscar, 1913-1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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