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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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Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor

Description: The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, forme… more
Date: December 20, 1961
Creator: Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid

Description: The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several type… more
Date: October 1, 1961
Creator: Clark, A. T., Jr.; Meyer, L. H.; Owen, J. H. & Rust, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compositional analysis technique for HNS/Kel-F 800

Description: A compositional analysis procedure for the plastic-bonded explosive consisting of HNS and Kel-F 800 is presented. The Kel-F is determined gravimetrically after extraction of the HNS with fuming nitric acid. The HNS content is calculated by difference.
Date: August 1, 1980
Creator: Sandoval, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development

Description: Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added … more
Date: May 15, 1962
Creator: Newby, B. J.
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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PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II

Description: Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphi… more
Date: November 30, 1961
Creator: Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Future aircraft and potential effects on stratospheric ozone and climate

Description: The purpose of this study is to extend the recent research examining the global environmental effects from potential fleets of subsonic and supersonic commercial aircraft. Initial studies with LLNL models of global atmospheric chemical, radiative, and transport processes have indicated that substantial decreases in stratospheric ozone concentrations could result from emissions of NO{sub x} from aircraft flying in the stratosphere, depending on fleet size and magnitude of the engine emissions. T… more
Date: October 1, 1991
Creator: Kinnison, D.E. & Wuebbles, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS

Description: Neptunium distribution coefficients from acid nitrate, chloride, and sulfate solutions by several organic nitiogen and phosphorus compounds were measured as functions of several extraction variables, including neptunium valence, acid and salt concentration, and reagent concentration. Extractability by all the reagents varied in the order Np(IV)> Np(VI)>> Np(V). Except for primary amines, all reagents extracted Np(IV) much more strongly from nitrate than sulfate solutions. Among organonitrogen c… more
Date: October 19, 1961
Creator: Weaver, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of filter media for clarification of partially dissolved residues containing plutonium

Description: A common process in the chemical industry employs the leaching of a desirable component from an insoluble substrate, followed by filtration to produce a clarified solution of the desirable component and a discardable residue. The work described here involved evaluating sintered metal filter media for separating dissolved plutonium from undissolved residues generated at various locations owned by the Department of Energy throughout the United States. The work was performed during a six-week assi… more
Date: October 9, 1989
Creator: Foley, E.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Waste acid detoxification and reclamation: Phase 1, Project planning and concept development

Description: The objectives of this project are to develop processes for reducing the volume, quantity, and toxicity of metal-bearing waste acids. The primary incentives for implemeting these types of waste minimization processes are regulatory and economic in that they meet requirements in the Resource Conservation and Recovery Act and reduce the cost for treatment, storage, and disposal. Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication oper… more
Date: February 1, 1988
Creator: Stewart, T. L. & Brouns, T. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

Description: A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring … more
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Equilibrium of the System Lanthanum Nitrate-Praseodymium Nitrate-Nitric Acid-Water-Tributyl Phosphate

Description: A study of the extraction characteristics of the three systems lanthanum nitrate--nitric acid--water--tributyl phosphate, praseodymium nitrate--nitric acid--water--tributyl phosphate, and lanthanum nitrate--praseodymium nitrate nitric acid -water--tributyl phosphate was conducted. The separation factors between praseodymium and lanthanum for the system lanthanum nitrate--praseodymium nitrate-nitric acid--water--tributyl phosphate were shown to be a function of the total nitrate concentration of… more
Date: November 1, 1960
Creator: Sharp, B. M. & Smutz, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction and recovery of plutonium and americium from nitric acid waste solutions by the TRUEX process - continuing development studies

Description: This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX pro… more
Date: September 1, 1985
Creator: Leonard, R. A.; Vandegrift, G. F.; Kalina, D. G.; Fischer, D. F.; Bane, R. W.; Burris, L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculated and experimental studies of nonequilibrium solvent extraction of uranium-thorium and uranium-zirconium

Description: The nonequilibrium simultaneous transfer of ions in solvent extraction has been examined experimentally and these results have been compared with the calculated behavior determined using transfer rate constants. In the Th-U system when transferring from 2 M HNO/sub 3/ into 30% tributyl phosphate (TBP) in normal hydrocarbon diluent (NPH), the thorium approaches equilibrium faster than uranium over much of the transfer region. Thus, nonequilibrium operation will not increase the separation factor… more
Date: January 1, 1980
Creator: Mailen, J. C. & Horner, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Use of the TRUEX process for the pretreatment of neutralized cladding removal waste (NCRW) sludge -- Results of FY 1990 studies

Description: The goal of this process is to separate the transuranic elements from the bulk components so that the bulk components can be disposed of as low-level waste with only a small transuranic-containing fraction requiring geologic disposal. The pretreatment process examined here is the one indicated to be most promising in the initial studies. It involves dissolving the unwashed sludge in nitric acid and then using the TRUEX solvent extraction process to remove the transuranic elements from the bulk … more
Date: September 1, 1991
Creator: Swanson, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LABORATORY DEVELOPMENT OF A CARRIER-PRECIPITATION PROCESS FOR THE RECOVERY OF STRONTIUM FROM PUREX WASTES

Description: Strontium recovery from Purex 1WW was investigated with simulated feeds and tracer activities. Initial experiments demonstrated recovery of over 70% of the strontium by sulfate precipitation from partially neutralized 1WW by either increasing the sulfate concentration to about 3 M or by adding carriers such as lead. Precipitation of iron was avoided by addition of one or more moles of tartrate per two moles of iron. Precipitation at elevated temperatures and addition of lead after pH adjustment… more
Date: May 1, 1961
Creator: Bray, L.A. & Van Tuyl, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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