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Reactor Development Program Progress Report: May 1966

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
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Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

Description: This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Description of the Thermal Hydraulics Laboratory at Hanford

Description: Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Date: June 2, 1960
Creator: Batch, J. M. & Toyoda, K. G.
Partner: UNT Libraries Government Documents Department
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A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals

Description: Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date: June 20, 1955
Creator: Been, Julian F.
Partner: UNT Libraries Government Documents Department
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The Shielding of Mobile Reactors - [Part] 2

Description: From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, ar… more
Date: June 30, 1952
Creator: Blizard, E. P. & Welton, T. A.
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966

Description: Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: June 1967
Creator: Borkowski, C. J.; Dandl, R. A.; Epler, E. P. & Harrill, C. S.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Briggs, R. B.
Partner: UNT Libraries Government Documents Department
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In-Pile Test of Prototype ML-1 Fuel Elements

Description: Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
Partner: UNT Libraries Government Documents Department
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Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Description: Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date: June 30, 1963
Creator: Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
Partner: UNT Libraries Government Documents Department
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Flora of Healthy Dogs: [Part] 2. Isolation of Enteroviruses from Lower Intestines

Description: Fecal specimens from apparently healthy dogs were inoculated into MK, DK, HeLa, and CP cells. Twenty-six cytopathic agents were isolated in MK, 11 in HeLa, and 4 in CP, but none in DK cells. Neutralization tests indicated that all but one of the viruses were either strains of ECHO type 6 or were closely related to it. Twenty-one of 29 dogs were carrying the virus.
Date: June 1963
Creator: Clapper, W. E. & Pindak, F. F.
Partner: UNT Libraries Government Documents Department
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Analog Models for HNPF Control and Protection Studies

Description: Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date: June 15, 1964
Creator: Dunsmore, C. L.
Partner: UNT Libraries Government Documents Department
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Boiling Songs and Associated Mechanical Vibrations

Description: From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.
Date: June 30, 1960
Creator: Firstenberg, H.
Partner: UNT Libraries Government Documents Department
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Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

Description: The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date: June 1965
Creator: Fletcher, R. D.
Partner: UNT Libraries Government Documents Department
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The Particulate State of Fission Products Released From Irradiated Uranium When Heated in Air: [Part ]1. Preliminary Results for I131, Te132, and Ru103

Description: From Introduction: "The present study was initiated to provide data regarding the particulate state of fission products released from uranium heated in air. It was expected that the information gained in this work would be valuable in planning experiments in which animals would be exposed to aerosols of mixed fission products and in determining the feasibility of using the effluent from a fuel specimen melt-down or oxidation in such exposures."
Date: June 1963
Creator: Gallimore, John C. & Mercer, T. T.
Partner: UNT Libraries Government Documents Department
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Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Description: Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
Partner: UNT Libraries Government Documents Department
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A New Model Concept for Large Nuclear Reactors

Description: Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Date: June 1964
Creator: Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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