Technical Report Archive & Image Library (TRAIL) - 110 Matching Results

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Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

Description: Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.
Date: May 26, 1958
Creator: Commonwealth Edison Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

Description: This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod

Description: Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.
Date: May 1962
Creator: Williamson, H.E. & Alexander, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bounce III

Description: BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date: December 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Collected Methods for Analysis of Sodium Metal

Description: Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.
Date: October 15, 1959
Creator: Perrine, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker

Description: The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date: August 8, 1960
Creator: Biglieri, N. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory

Description: Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.
Date: February 1961
Creator: Brandt, F. A.; Mathay, P. W. & Zimmerman, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Worth of B4C Rods

Description: This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.
Date: August 30, 1961
Creator: Pomraning, G. C. (Gerald C.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Report: Superheat Strain - Cycle Capsule

Description: In order to investigate the low frequency strain cycle fatigue for tubular sheath geometries an apparatus was designed and fabricated for laboratory and reactor experiments. The design of this apparatus is described herein.
Date: January 1963
Creator: Marburger, L.L.; Haglund, E. A.; Hafer, D. E.; Liffengren, D. J. & Armour, S. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Determination of Fission Product Gamma Doses

Description: In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.
Date: February 25, 1957
Creator: Ruehle, William G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Economic Evaluation of Control Rod Materials and Fabrication Processes

Description: Control rod materials, designs, and fabrication processes are compared for their relative economies. Control rod lifetime data are calculated with a simple approximation of nuclear worth depreciation. These data are used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime is included.
Date: May 1962
Creator: Williamson, H. E. & Megerth, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Enclosure Pressure Calculation Method

Description: A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.
Date: October 6, 1956
Creator: Bailey, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station

Description: The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site near the confluence of the Kankakee and Des Plaines Rivers in Grundy County, Illinois, about 47 miles southwest of Chicago. The plant will be known as the Dresden Nuclear Power Station, and will employ a nuclear reactor of the dual-cycle boiling water type.
Date: January 24, 1957
Creator: Commonwealth Edison Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Erosion Experiments of Powder Compacted Uranium Dioxide Under Dynamic Steam Flow (Preliminary Report)

Description: Experiments were carried out to determine the erosion, oxidation and dimensional characteristics of purposely defected fuel elements containing unsintered UO2 powder prepared by the swaging technique. The experiments were conducted in an out-of-reactor loop under superheat conditions of pressure, temperature, flow velocity and steam chemical composition.
Date: March 21, 1961
Creator: Spalaris, C. N.; Comprelli, F. A. & Siegler, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961

Description: The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date: April 24, 1962
Creator: Horst, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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