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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; 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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Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962

Description: In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date: August 23, 1962
Creator: Whatley, M. E.; 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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Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961

Description: An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomp… more
Date: January 23, 1962
Creator: Whatley, M. E.; 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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Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961

Description: The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engi… more
Date: December 26, 1961
Creator: Whatley, M. E.; 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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Chemical Technology Division Unit Operations Section Monthly Progress Report, April 1962

Description: Bubble size measurements in the foam column showed that a spinnerette with 50 mu holes gave a nearly normal distribution of bubbles sizes while a coarse fritted glass gas sparger had a tail of large bubbles which did not fit the normal curve. A set of equations solvable by a finite difference technique are presented which completely describe the irreversible reaction rate of H/sub 2/ or CO with a fixed bed of CuO pellets. Radiation damage tests are in progress to evaluate plastics for the Trans… more
Date: October 1, 1962
Creator: Whatley, M. E.; 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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Chemical Technology Division, Unit Operations Section Monthly Progress Report, August 1961

Description: Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. d… more
Date: March 1, 1962
Creator: Whatley, M. E.; 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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Tests of a Higgins contactor for the engineering-scale resin loading of uranium

Description: The loading of uranium on weak-acid ion exchange resin is a basic step in the production of fuel particles for high-temperature gas-cooled reactors (HTGRs). In the work reported here, an engineering-scale continuous resin loader (2-in.-ID Higgins contactor) was tested with existing engineering-scale process equipment. The Higgins contactor was first successfully used to convert Na/sup +/-form resin to the H/sup +/-form; then it was evaluated as a uranium loader. Results show that the 2-in.-ID H… more
Date: January 1, 1978
Creator: Spence, R. D. & Haas, P. 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 1961

Description: Openation of a 6-in.-dia foam separation column with Sr/sup 89/ tracer and dodecylbenzenesulfonate as a surfactant and foaming agent was continued. The catalytic oxidation of H/sub 2/, CO, and CH/sub 4/ was studied using a nickel- chromepalladium ribbon catalyst. A Mark I prototype fuel assembly was sheared to within 1.5-in. of the end by modifying the gas hydraulic system of the shear. The force required to shear a highly carburized Mark I fuel assembly ductile tubing. Demonstration of the mec… more
Date: May 16, 1962
Creator: Whatley, M. E.; 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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Literature information applicable to the reaction of uranium oxides with chlorine to prepare uranium tetrachloride

Description: The reaction of uranium oxides and chlorine to prepare anhydrous uranium tetrachloride (UCl{sub 4}) are important to more economical preparation of uranium metal. The most practical reactions require carbon or carbon monoxide (CO) to give CO or carbon dioxide (CO{sub 2}) as waste gases. The chemistry of U-O-Cl compounds is very complex with valances of 3, 4, 5, and 6 and with stable oxychlorides. Literature was reviewed to collect thermochemical data, phase equilibrium information, and results … more
Date: February 1, 1992
Creator: Haas, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

Description: The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the deve… more
Date: December 1, 1993
Creator: Bell, J. T.; Haas, P. A. & Rudolph, J. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Molten salt oxidation of mixed waste: Preliminary bench-scale experiments without radioactivity

Description: Molten salt oxidation (MSO) is a process in which organic wastes are oxidized by sparging them with air through a bed of molten sodium carbonate (bp 851 {degrees}C) at {ge} 900{degrees}C. This process is readily applicable to the mixed waste because acidic products from Cl, S, P, etc., in the waste, along with most metals and most radionuclides, are retained within the melt as oxides or salts. Rockwell International has studied the application of MSO to various wastes, including some mixed wast… more
Date: June 1, 1994
Creator: Haas, P. A.; Rudolph, J. C. & Bell, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Catalyzed reduction of nitrate in aqueous solutions

Description: Sodium nitrate and other nitrate salts in wastes is a major source of difficulty for permanent disposal. Reduction of nitrate using aluminum metal has been demonstrated, but NH{sub 3}, hydrazine, or organic compounds containing oxygen would be advantageous for reduction of nitrate in sodium nitrate solutions. Objective of this seed money study was to determine minimum conditions for reduction. Proposed procedure was batchwise heating of aqueous solutions in closed vessels with monitoring of tem… more
Date: August 1, 1994
Creator: Haas, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and test of a thermosiphon evaporator for acid-deficient uranyl nitrate

Description: The reference process to recycle /sup 233/U to HTGRs begins with the receipt of the /sup 233/UO/sub 2/(NO/sub 3/)/sub 2/ product solution from a reprocessing plant, which is fed to a resin loading system. The nitrate is removed by extraction with a liquid organic amine. By adding an evaporator to remove water, a continuous, high-efficiency process for loading uranium on ion exchange resin is possible. A vertical thermosiphon evaporator was designed, fabricated, and tested with natural uranium t… more
Date: November 1, 1976
Creator: Drago, J. P. & Haas, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Resin-based preparation of HTGR fuels: operation of an engineering-scale uranium loading system

Description: The fuel particles for recycle of /sup 233/U to High-Temperature Gas-Cooled Reactors are prepared from uranium-loaded carboxylic acid ion exchange resins which are subsequently carbonized, converted, and refabricated. The development and operation of individual items of equipment and of an integrated system are described for the resin-loading part of the process. This engineering-scale system was full scale with respect to a hot demonstration facility, but was operated with natural uranium. The… more
Date: October 1, 1977
Creator: Haas, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Drying of ion-exchange resins for resin-based preparation of nuclear reactor fuels

Description: The reference fuel kernel for recycle of /sup 233/U to HTGRs (High Temperature Gas-Cooled Reactors) is prepared by loading carboxylic acid cation-exchange resins with uranium and carbonizing at controlled conditions. The loaded, dried resin must meet specifications for sphericity, composition, and other properties. Microwave heating is used to give controlled and reproducible drying of 11-liter batches of uranium-loaded (4 kg of uranium) resin in a vessel of safe dimensions for nuclear critical… more
Date: January 1, 1976
Creator: Drago, J. P.; Haas, P. A. & Million, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reaction of uranium oxides with chlorine and carbon or carbon monoxide to prepare uranium chlorides

Description: The preferred preparation concept of uranium metal for feed to an AVLIS uranium enrichment process requires preparation of uranium tetrachloride (UCI{sub 4}) by reacting uranium oxides (UO{sub 2}/UO{sub 3}) and chlorine (Cl{sub 2}) in a molten chloride salt medium. UO{sub 2} is a very stable metal oxide; thus, the chemical conversion requires both a chlorinating agent and a reducing agent that gives an oxide product which is much more stable than the corresponding chloride. Experimental studies… more
Date: November 1, 1991
Creator: Haas, P. A.; Lee, D. D. & Mailen, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Drying of uranium-loaded cation exchange resin with microwave heating

Description: The reference fuel kernel for recycle of /sup 233/U to HTGRs (High-Temperature Gas-Cooled Reactors) is prepared by loading carboxylic acid cation exchange resin with uranium and carbonizing it at controlled conditions. The wet, uranium-loaded resin must be dried to a water content of 10 to 16 wt percent prior to carbonization to minimize handling problems. Microwave heating was demonstrated to give controlled and reproducible dried resin in a vessel whose dimensions were safe for nuclear critic… more
Date: December 1, 1976
Creator: Drago, J. P. & Haas, P. A.
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 for February 1959

Description: A gamma scintillation spectrometer was used to measure diffusivity of uranyl nitrate in water during preliminary capillary experiments. During Fluorox run FBR-22, 90.4% of the theoretical amount of UF/sub 6/ formed was collected in cold traps and chemical traps. Toroid tests of flame calcined mixed Th-U oxide showed low corrosion rates, small changes in particle size and a low solubilization of uranium, while denitration of uranyl nitrate in a fluidized bed resulted in particle growth with unif… more
Date: June 11, 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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Chemical Technology Division, Unit Operations Section Monthly Progress Report for June 1959

Description: The addition of a surface active agent to an aqueousorganic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2-in. thick MgO liners and terminated due to either failures of the UF/sub 6/ 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… more
Date: September 1, 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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HRP-CP: Conclusions Concerning the Predicted Behavior of Insoluble Corrosion and Fission Products in the HRT

Description: Information available from HRP-CP development studies was summarized amd used as a basis for predicting the probable behavior of corrosion and fission product solids in the HRT and its associated chemical processing plant. Operation of the chemical plant will probably limit the HRT circulating solids concentration to between 10 and 100 ppm; quantitative predictions are uncertain due to uncertainties concerning the charaeteristics of reactor solids and the effects of rcactor geometries. (auth)
Date: January 23, 1958
Creator: Haas, P. A.; Horton, R. W. & McNees, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP-CPP: Dissolution of Zirconium and stainless steel corrosion product oxides

Description: Dissolution methods were developed to permit representative sampling of the slurry of corrosion and fission products collected by the HRT chemical process-ing plant. The procedure selected for HRT-CPP application was to use 15 ml of 10.8 M H/sub 2/SO/sub 4/ per gram of solids with agitation by boiling in a tantalum-lined dissolver. (auth)
Date: August 1, 1958
Creator: Snider, J. W. & Haas, P. A.
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 1962

Description: The development of foam separation as a unit operation was considered from the distributor design and gas rate standpoints. The development of a shear and leach process for power reactor fuel processing is reported in which carburized Yankee prototype fuel assemblies were sheared to determine the effect of fuel element condition on the nature of the chopped pieces. A Squarkeen No. 3 moving blade lasted for 5894 cuts while a Kleencut blade failed at 320 cuts under normal program use. A plastics … more
Date: January 29, 1963
Creator: Whatley, M. E.; 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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