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Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962
Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
Date:
December 1, 1962
Creator:
Rider, B. F.; Ruiz, C. P. & Peterson, J. P.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses: Third Quarterly Progress Report June - August, 1962
Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed by the third quarter of 1962 is summarized.
Date:
October 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station
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
System:
The UNT Digital Library
Amendment No. 2 To License Application For Nuclear Test Reactor
GE is amending its application of 6/5/57 to construct and operate the Nuclear Test Reactor in order to incorporate changes in procedure and equipment.
Date:
October 7, 1958
Creator:
General Electric Company
System:
The UNT Digital Library
Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station
This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.
Date:
August 25, 1958
Creator:
Commonwealth Edison Company
System:
The UNT Digital Library
Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station
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
System:
The UNT Digital Library
Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod
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.
System:
The UNT Digital Library
Bounce III
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.
System:
The UNT Digital Library
Burnout Conditions for Nonuniformly Heated Rod in Annular Geometry, Water at 1000 PSIA
Tests were run at the General Electric Company, Atomic Power Equipment Department, to determine the burnout conditions for a non-uniformly heated rod in an annular geometry.
Date:
June 1963
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
Calculated Scattering Kernels For Light Water at 23C, 42C, 61C, and 82C
This report contains a listing of the bound-proton kernels for neutron scattering which were calculated in conjunction with the USAEC Control Rod Materials Program.
Date:
May 27, 1962
Creator:
Kerr, B. A.
System:
The UNT Digital Library
Collected Methods for Analysis of Sodium Metal
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.
System:
The UNT Digital Library
Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker
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.
System:
The UNT Digital Library
Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory
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.
System:
The UNT Digital Library
Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model
Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.
Date:
September 1961
Creator:
Swan, C. L.
System:
The UNT Digital Library
Consumers Big Rock Point Nuclear Power Reactor Stability Analysis
This report presents the results of an analysis which was undertaken to investigate the power stability of the Consumers Big Rock Point Nuclear Power Reactor.
Date:
1964?
Creator:
Case, J. M. & Holland, L. K.
System:
The UNT Digital Library
Control Worth of B4C Rods
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.)
System:
The UNT Digital Library
Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)
Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience with over-all reactor system is also discussed."
Date:
February 1965
Creator:
Ianni, P. W.; Fritz, J. R. & Law, D. D.
System:
The UNT Digital Library
Design Report: Superheat Strain - Cycle Capsule
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.
System:
The UNT Digital Library
The Determination of Fission Product Gamma Doses
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.
System:
The UNT Digital Library
The Development of a Scheduling Computer For The Big Rock Plant
The basic work for development of a scheduling computer for the Consumers' Big Rock Plant is outlined in this report. The computer's purpose is to make feasible higher power densities by operation closer to fuel element burnout limits, and to maximize fuel burnup.
Date:
1961
Creator:
Beckjord, Eric S.
System:
The UNT Digital Library
Economic Evaluation of Control Rod Materials and Fabrication Processes
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.
System:
The UNT Digital Library
Enclosure Pressure Calculation Method
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.
System:
The UNT Digital Library
Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station
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
System:
The UNT Digital Library
Erosion Experiments of Powder Compacted Uranium Dioxide Under Dynamic Steam Flow (Preliminary Report)
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.
System:
The UNT Digital Library