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Recovery of plutonium and americium from chloride salt wastes by solvent extraction

Description: Plutonium and americium can be recovered from aqueous waste solutions containing a mixture of HCl and chloride salt wastes by the coupling of two solvent extraction systems: tributyl phosphate (TBP) in tetrachloroethylene (TCE) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in TCE. In the flowsheet developed, the salt wastes are dissolved in HCl, the Pu(III) is oxidized to the IV state with NaClO/sub 2/ and recovered in the TBP-TCE cycle, and the Am is then removed from t… more
Date: January 1, 1987
Creator: Reichley-Yinger, L. & Vandegrift, G.F.
Partner: UNT Libraries Government Documents Department
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Multiheteromacrocycles that complex metal ions. Sixth progress report, 1 May 1979-30 April 1980. [Hemispherands; spherands]

Description: Objective is to design synthesize, and evaluate cyclic and polycyclic host organic compounds for their abilities to complex and lipophilize guest metal ions, their complexes, and their clusters. Host organic compounds consist of strategically placed solvating, coordinating, and ion-pairing sites tied together by covalent bonds through hydrocarbon units around cavities shaped to be occupied by guest metal ions or by metal ions plus their ligands. Specificity in complexation is sought by matching… more
Date: January 15, 1980
Creator: Cram, D. J.
Partner: UNT Libraries Government Documents Department
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Exploratory research on solvent refined coal liquefaction. Annual technical progress report, January 1-December 31, 1979

Description: This report summarizes the progress of the Exploratory Research on Solvent Refined Coal Liquefaction project by The Pittsburg and Midway Coal Mining Co.'s Merriam Laboratory during 1979. In a series of experiments with varying feed gas composition, low levels (5 to 10 mole %) of carbon monoxide had little effect on the SRC II processing of Pittsburgh Seam coal (Powhatan No. 5 Mine) while higher levels (20 to 40 mole %) resulted in a general degradation of operability and reduced oil yields. Add… more
Date: September 1, 1980
Partner: UNT Libraries Government Documents Department
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Size selective synergism by crown ethers in the extraction of alkali metals by di(2-ethylhexyl) phosphoric acid

Description: Although the macrocyclic polyethers, known as crown ethers, complex metal ions and do so preferentially according to the size correspondance between the ion and the crown ether cavity, their usefulness as liquid-liquid extraction reagents has been limited by the necessity of solubilizing the anion in the organic phase. The common mineral acid anions are difficult to transfer to the organic phase and organophilic anions are expensive or impractical. A method is described that avoids this problem… more
Date: January 1, 1980
Creator: McDowell, W.J.; Kinard, W.F. & Shoun, R.R.
Partner: UNT Libraries Government Documents Department
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Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

Description: This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.
Date: September 1, 1980
Partner: UNT Libraries Government Documents Department
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Process and analytical studies of enhanced low severity co-processing using selective coal pretreatment

Description: This report describes progress on research during the eleventh quarter of this contract dealing with applications of coal pretreatment techniques in coal/oil co-processing and direct hydroliquefaction. The objectives of the project are to investigate various coal pretreatment techniques and to determine the effect of these pretreatment procedures on the reactivity of the coal. Reactivity enhancement will be evaluated under both direct hydroliquefaction and co-processing conditions. Coal convers… more
Date: 1991-06~
Creator: Baldwin, R. M.; Gaur, S. & Miller, R. L.
Partner: UNT Libraries Government Documents Department
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HTGR fuel recycle program. Quarterly progress report for the period ending November 30, 1977

Description: The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to … more
Date: December 1, 1977
Partner: UNT Libraries Government Documents Department
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Robotic sample preparation for radiochemical plutonium and americium analyses

Description: A Zymate robotic system has been assembled and programmed to prepare samples for plutonium and americium analyses by radioactivity counting. The system performs two procedures: a simple dilution procedure and a TTA (xylene) extraction of plutonium. To perform the procedures, the robotic system executes 11 unit operations such as weighing, pipetting, mixing, etc. Approximately 150 programs, which require 64 kilobytes of memory, control the system. The system is now being tested with high-purity … more
Date: January 1, 1985
Creator: Stalnaker, N.; Beugelsdijk, T.; Thurston, A. & Quintana, J.
Partner: UNT Libraries Government Documents Department
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Sampling and analysis of trace-organic constituents in ambient and workplace air at coal-conversion facilities

Description: A review of the recent literature reveals that current sampling procedures involve the use of glass fiber filters for particulate-sorbed organics and sorbent resins such as Tenax GC and XAD-2 for vapor-phase organics. Ultra trace-organic analysis of air pollutants or particulates may require the collection of a large (1000 to 3000 m/sup 3/) sample by a high volume air sampler. Personal air sampling requires a smaller (approx. = 0.5 m/sup 3/) and a portable collection apparatus. Trapped organic … more
Date: July 1, 1980
Creator: Flotard, R D
Partner: UNT Libraries Government Documents Department
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Volatilities of ruthenium, iodine, and technetium on calcining fission product nitrate wastes

Description: Various high-level nitrate wastes were subjected to formic acid denitration. Formic acid reacts with the nitrate anion to yield noncondensable, inert gases according to the following equation: 4 HCOOH + 2 HNO/sub 3/ ..-->.. N/sub 2/O + 4 CO/sub 2/ + 5 H/sub 2/O. These gases can be scrubbed free of /sup 106/Ru, /sup 131/I, and /sup 99/Tc radioactivities prior to elimination from the plant by passage through HEPA filters. The formation of deleterious NO/sub x/ is avoided. Moreover, formic acid re… more
Date: January 1, 1980
Creator: Rimshaw, S. J. & Case, F. N.
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.
Partner: UNT Libraries Government Documents Department
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Actinide partitioning and transmutation program. Progress report, July 1--September 30, 1977

Description: In Purex process modifications, two cold runs with mixer-settlers were made on the extraction and stripping of ruthenium and zirconium without the presence of uranium. Efforts in actinide recovery from solids were directed toward the determination of dissolution parameters in various reagents for /sup 241/Am and /sup 239/Pu oxide mixtures, /sup 233/U oxide, /sup 237/Np oxide, /sup 244/Cm oxide, /sup 232/Th oxide, and PuO/sub 2/. Studies in americium-curium recovery with OPIX (oxalate precipitat… more
Date: February 1, 1978
Creator: Tedder, D.W. & Blomeke, J.O. (comps.)
Partner: UNT Libraries Government Documents Department
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Determination of trace impurities in uranium hexafluoride by an inductively coupled argon plasma spectrometer

Description: A procedure has been developed to determine 21 trace impurity elements in uranium hexafluoride, using inductively coupled argon plasma emission spectrometry (ICAP). The method consists of a liquid-liquid extraction to separate uranium from the trace impurities with a mixture of tri-(2-ethyl-hexyl)-phosphate (TEHP) and heptane. The raffinate containing the elements is subsequently analyzed by ICAP. The impurity elements which can be analyzed by this method are: Al, B, Ba, Be, Bi, Ca, Cd, Co, Cr,… more
Date: January 6, 1983
Creator: Short, B. W.; Spring, H. S. & Grant, R. L.
Partner: UNT Libraries Government Documents Department
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Treatment of radioactive mixed wastes in commercial low-level wastes

Description: Management options for three generic categories of radioactive mixed waste in commercial low-level wastes have been identified and evaluated. These wastes were characterized as part of a BNL study in which a large number of generators were surveyed for information on potentially hazardous low-level wastes. The general management targets adopted for mixed wastes are immobilization, destruction, and reclamation. It is possible that these targets may not be practical for some wastes, and for these… more
Date: January 1, 1985
Creator: Kempf, C.R. & MacKenzie, D.R.
Partner: UNT Libraries Government Documents Department
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Coal liquefaction process streams characterization and evaluation

Description: This study was designed to demonstrate the use of two different methods for the separation of direct coal liquefaction process- derived materials into defined fractions. The two methods, liquid chromatography (LC) and supercritical fluid extraction (SFE), were employed to determine if the same or complementary information could be obtained by the two methods. The primary objective was to evaluate the potential of supplementing or replacing the conventional LC method with SFE and in so doing to … more
Date: January 1, 1992
Creator: Taylor, L. T.; Hellgeth, J. W. & Sequeira, A.
Partner: UNT Libraries Government Documents Department
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Secondary recovery of plutonium and americium from process waste streams by solvent extraction

Description: A solvent extraction process is being evaluated for the secondary recovery of plutonium and americium from Rocky Flats waste streams. The bidentate organophosphorus compounds dihexyl-N,N-diethylcarbamylmethylene phosphonate and its dibutyl analogue have been shown to be selective extractants for the actinides from solutions of nitric acid. The results from laboratory test runs in which the organophosphorus extractants were used for processing secondary waste solutions will be presented. Solvent… more
Date: January 16, 1978
Creator: Hagan, P. G. & Navratil, J. D.
Partner: UNT Libraries Government Documents Department
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Characterization of nitrogen compound types in hydrotreated Paraho shale oil

Description: Results from the separation and characterization of nitrogen compound types in hydrotreated Paraho shale oil samples were obtained. Two samples of Paraho shale oil were hydrotreated by Chevron Research Company such that one sample contained about 0.05 wt. percent nitrogen and the other sample contained about 0.10 wt. percent nitrogen. A separation method concentrate specific nitrogen compound types was developed. Characterization of the nitrogen types was accomplished by infrared spectroscopy, … more
Date: October 1, 1980
Creator: Holmes, S.A. & Latham, D.R.
Partner: UNT Libraries Government Documents Department
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HTGR fuel recycle program. Quarterly progress report for the period ending August 31, 1977

Description: The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to … more
Date: September 1, 1977
Partner: UNT Libraries Government Documents Department
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Alternate fuel cycle technologies. Quarterly report, April--June 1977

Description: This quarterly report describes studies to provide information needed to close the back end of the commercial light-water reactor (LWR) fuel cycle. These efforts are directed primarily at reprocessing and recycle of uranium and plutonium from spent LWR fuel. Research is reported in the following categories: environmental studies, fuel receipt, head-end processes, purex process, waste management, safeguards (dose rate for extraction streams), and general support.
Date: September 1, 1977
Partner: UNT Libraries Government Documents Department
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Experimental studies at the Idaho Chemical Processing Plant on actinide partitioning from acidic nuclear wastes

Description: Wastes generated at ICPP and in the reprocessing of LWR fuel is discussed separately. DHDECMP is used as extractant. Studies on DHDECMP purification and toxicity, diluent effects, reaction kinetics, radioloysis, mixer-settler performance, etc. are reported. 10 tables, 3 figures. (DLC)
Date: January 1, 1980
Creator: McIssaac, L.D.; Baker, J.D.; Meikrantz, D.H. & Schroeder, N.C.
Partner: UNT Libraries Government Documents Department
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Americium purification by a combined anion exchange and bidentate organophosphorus solvent extraction process. [Patent application]

Description: Americium is separated from mixtures containing plutonium, other actinides, and other non-lanthamide impurities, by a combined process of anion exchange resin sorption to remove plutonium, and a bidentate organophosphorus solvent extraction of americium of the anion exchange resin effluent. Dihexyl-N,N-diethylcarbamylmethylenephosphonate is a preferred solvent. The initial mixture may be subjected to a cation exchange operation to remove monovalent impurities. The process is especially effectiv… more
Date: April 10, 1981
Creator: Navratil, J.D. & Martella, L.L.
Partner: UNT Libraries Government Documents Department
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Pilot plant studies of the bioconversion of cellulose and production of ethanol

Description: Progress is reported in the following studies on analysis and evaluation of potential raw materials: preliminary pretreatment studies using wheat straw; extraction of wheat straw with alcohol and water at elevated temperatures; extraction of ground wood with alcohol and water at elevated temperatures; and, delignification of newsprint with ethylene glycol. Other research in progress includes studies on: utilization of hemicellulose sugars; process design and economics of hydrolysis processes an… more
Date: June 30, 1977
Creator: Wilke, C.R.
Partner: UNT Libraries Government Documents Department
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Procedure for the analysis of americium in complex matrices

Description: A radioanalytical procedure for the analysis of americium in complex matrices has been developed. Clean separations of americium can be obtained from up to 100 g of sample ash, regardless of the starting material. The ability to analyze large masses of material provides the increased sensitivity necessary to detect americium in many environmental samples. The procedure adequately decontaminates from rare earth elements and natural radioactive nuclides that interfere with the alpha spectrometric… more
Date: February 1, 1978
Creator: Knab, D.
Partner: UNT Libraries Government Documents Department
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Comparative Evaluation of DHDECMP (dihexyl-N,N-diethylcarbamoyl-methylphosphonate) and CMPO (octylphenyl-N,N,-diisobutylcarbamoylmethylphosphine oxide) as Extractants For Recovering Actinides From Nitric Acid Waste Streams

Description: Certain neutral, bifunctional organophosphorous compounds are of special value to the nuclear industry. Dihexyl-N,N-diethylcarbomoylmethylphosphonate (DHDECMP) and octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) are highly selective extractants for removing actinide and lanthanide elements from nitric acid. We obtained these two extractants from newly available commercial sources and evaluated them for recovering Am(III), Pu(IV), and U(VI) from nitric acid waste streams of pluto… more
Date: February 1, 1988
Creator: Marsh, S.Fredric & Yarbro, Stephen L.
Partner: UNT Libraries Government Documents Department
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