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Process Engineering Report on Production of Thorium at Iowa State College

Description: Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
Date: January 16, 1952
Creator: Bulkowski, H. H.; Holby, G. V.; Pfeiffer, C.; Maerker, J. B. & Winn, F. W.
Partner: UNT Libraries Government Documents Department
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FMPC Solvent Treatment Area - Process Design

Description: This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date: July 6, 1951
Creator: Pfeiffer, Carl & Maerker, John B.
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: 1965

Description: Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.
Date: November 10, 1965
Creator: North American Aviation. Atomics International Division.
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: 1966

Description: Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.
Date: August 31, 1966
Creator: North American Aviation. Atomics International Division.
Partner: UNT Libraries Government Documents Department
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Results of exploration at Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, July 1951-February 1952: an interim report

Description: "his interim report presents the grade and tonnage data collected during exploration at the Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, Between July 1951 and February 1952. Discussions of he geologic results of exploration (lithology, mineralogy, structure, origin, etc.) are not included in this report and consequently the detailed lithology and structure have been omitted from the illustrations (figs. 1-7)"
Date: July 1952
Creator: Sheridan, Douglas M.; Collier, John T. & Sears, Richard S.
Partner: UNT Libraries Government Documents Department
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Safety Evaluation of PNPF Modifications

Description: "The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."
Date: May 1, 1969
Creator: Huntsinger, M. & Hart, R. S.
Partner: UNT Libraries Government Documents Department
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High heat flux heater development status report

Description: The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.
Date: June 15, 1968
Creator: McKisson, R. L. & Babbe, E. L.
Partner: UNT Libraries Government Documents Department
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Doppler and related measurements in a soft fast-reactor spectrum

Description: This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
Date: March 24, 1969
Creator: Springer, T. H.; Tuttle, R. J.; Otter, J. M. & Pachall, R. K.
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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The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation

Description: An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
Date: June 25, 1953
Creator: Newell, Donald M.
Partner: UNT Libraries Government Documents Department
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The Anodizing of Zirconium

Description: Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.
Date: November 3, 1953
Creator: Ray, William E.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV

Description: Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nu… more
Date: March 30, 1961
Creator: Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
Partner: UNT Libraries Government Documents Department
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Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups

Description: Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel m… more
Date: March 31, 1962
Creator: Sontheimer, K. C.; Kemp, S. N.; Lois, L.; Clancy, E. F. & McCool, W. J.
Partner: UNT Libraries Government Documents Department
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Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants

Description: Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and… more
Date: January 23, 1962
Creator: Haraway, E. S. & Saccocio, R. M.
Partner: UNT Libraries Government Documents Department
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PM-2A Core II Zero Power Experiment

Description: Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of exper… more
Date: March 30, 1962
Creator: Walthousen, L. D.; Mageean, J. V.; Raby, T. M. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
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Sigma Plug Welding of Spun-Over Fuel Cans

Description: Summary: Purpose of the investigation is to improve the peripheral welding of the brazed joint at the top of aluminum-sheathed fuel slugs by forming the can over the top of the cap and welding the resulting center opening. This investigation looked at the applicability of the inert-gas-shielded, consumable electrode process, using commercially available equipment, for producing a weld closure in spun-over fuel cans. Using commercially available sigma welding equipment, no practical combinatio… more
Date: 1952
Creator: Winsor, F. J.
Partner: UNT Libraries Government Documents Department
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