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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fleet servicing facilities for servicing, maintaining, and testing rail and truck radioactive waste transport systems: functional requirements, technical design concepts and options cost estimates and comparisons

Description: This is a resource document which examines feasibility design concepts and feasibility studies of a Fleet Servicing Facility (FSF). Such a facility is intended to be used for routine servicing, preventive maintenance, and for performing requalification license compliance tests and inspections, minor repairs, and decontamination of both the transportation casks and their associated rail cars or tractor-trailers. None of the United States' waste handling plants presently receiving radioactive was… more
Date: May 1, 1980
Creator: Watson, C. D.; Hudson, B. J.; Keith, D. A.; Preston Jr., M. K.; McCreery, P. N.; Knox, W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Line focus solar thermal central receiver research study. Final report, April 30, 1977-March 30, 1979

Description: The results of a study to examine the line focus central receiver alternative for solar thermal generation of electric power on a commercial scale are presented. The baseline concept consists of the following elements: (1) a solar collector (heliostat) whose geometry is the equivalent of a focused parabolic cylinder. The heliostat reflecting surface is composed of an array of flexible rectangular mirror panels supported along their long edges by a framework which rotates about an axis parallel … more
Date: April 1, 1979
Creator: Di Canio, D. G.; Treytl, W. J.; Jur, F. A. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38. Revision 1

Description: An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: September 1, 1979
Creator: Box, W. D.; Shappert, L. B.; Seagren, R. D.; Watson, C. D.; Hammond, C. R. & Klima, B. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container

Description: An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable r… more
Date: January 1, 1980
Creator: Box, W. D.; Shappert, L. B.; Seagren, R. D.; Klima, B. B.; Jurgensen, M. C.; Hammond, C. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

Description: An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: August 1, 1979
Creator: Box, W. D.; Klima, B. B.; Seagren, R. D.; Shappert, L. B.; Watson, C. D. & Aramayo, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Engineering Section semiannual progress report (excluding reactor programs), March 1, 1975--August 31, 1975

Description: Sections are included on centrifugal analyzer development, advanced analytical techniques, bioengineering research and development, environmental studies, chemical engineering research, controlled thermonuclear processing, and coal conversion process development. A separate abstract was prepared for each section. (JRD)
Date: September 1, 1976
Creator: Scott, C. D.; Burtis, C. A.; Groenier, W. S.; Pitt, W. W.; Ryon, A. D.; Watson, C. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, September 1959, Chemical Technology Division

Description: Progress is reported on chemical reactor research, Druhm, HR thorium blanket studies, ion exchange, power reactor fuel reprocessing, volatility, waste processing.
Date: September 1959
Creator: Bresee, J. C.; Blomeke, J. O.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Watson, C. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination and Corrosion Resistance Properties of Selected Laboratory Surfaces

Description: This report presents decontamination and corrosion resistance data on various industrial materials tested on a laboratory scale to aid in the section of materials for the construction and maintenance of radiochemical laboratories at Oak Ridge National Laboratory.
Date: August 29, 1950
Creator: Watson, C. D.; Handley, T. H. & West, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report November 1959 - Chemical Technology Division

Description: Progress is reported on chemical engineering research, GCR coolant purification, HR thorium blanket studies, ion exchange, power reactor fuel processing, solvent extraction studies, volatility and waste processing.
Date: November 1959
Creator: Bresee, J. C.; Blomeke, J. O.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Watson, C. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recent Developments in Thorium Fuel Processing

Description: The following report summarizes the information on a year-long development of thorium fuel processing studies that took place at Oak Ridge National Laboratory.
Date: January 1, 1966
Creator: Nicholson, E. L.; Ferris, L. M.; Flanary, J. R.; Goode, J. H.; Hannaford, B. A.; Landry, J. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Processing of Thorium Fuels, Part 2

Description: The status of aqueous processing methods for tharium fuels is reviewed. A specially designed 250-ton shear was successfully tested for shearing full-size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths.
Date: June 7, 1963
Creator: Blanco, R. E.; Ferris, L. M.; Watson, C. D. & Rainey, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report June 1956

Description: The primary objective of this report is the monthly distribution of experimental data as acquired during that period in the course of engineering studies. Much of the data is of preliminary nature and, therefore, reasonable care should be exercised in its application. You are invited to contact the individual authors for substantiation.
Date: June 1, 1956
Creator: Eister, W. K.; Long, J. T.; Nurmi, E. O.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report July 1959

Description: A Lucite model of a multi-stage countercurrent hydroclone solvent extraction apparatus has been constructed and tested with Amsco-water. The diffusivity of Cs 134 tracer in aqueous chloride solution was measured to check the performance of the capillary diffusivity measuring system. The experimental data from four Druhm runs showed that 1/8in. thick graphite liners are usable for reactor temperatures above the boiling point of sodium.
Date: October 9, 1959
Creator: Bresee, J. C.; Haas, P.A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An analysis of power reactor fuel reprocessing

Description: This report presents an analysis of the projected economies and processing capacity requirements for a power reactor fuel reprocessing industry based on the recovery of fertile and fissionable materials from presently proposed power reactors within tbe confines of the continental United 8tates for the next five to ten years. An analysis of the present general state of development of a technology required for such an Industry is given. A summary of results of power reactor reprocessing chemical … more
Date: March 27, 1957
Creator: Culler, Jr., F. L.; Blanco, R. E.; Goeller, H. E. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report June 1959

Description: The addition of a surface active agent to an aqeous-organic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2in. thick MgO liners and terminated due to either failures of the UFe nozzle or a top gasket leak. In preliminary scale-up tests of the flame calcination equipment, a maximum feed rate equivalent to 720 g oxides/hr was achieved using a 3-in. i.d. magnesia reflector with an outside wall temper… more
Date: September 4, 1959
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D.; Whatley, M. E. & Horton, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Description: Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unit Operations Section Monthly Progress Report February 1960 - Chemical Technology Division

Description: Summaries of progress are presented for Fuel cycle development, GCR coolant clean up studies, HR Thorium blanket studies, Ion exchange, Power reactor fuel processing, Solvent extraction studies, Volatility, and Waste processing
Date: May 18, 1960
Creator: Whatley, M. E. (Marvin E.), 1926-; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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