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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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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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Recovery of plutonium from HEPA filters by Ce(IV): promoted dissolution of PuO/sub 2/ and recycle of the cerium promoter

Description: Studies carried out in this investigation included (1) electrolytic production of Ce(IV) from Ce(III), (2) leaching of refractory PuO/sub 2/ from HEPA filters with maintenance of Ce(IV) by anodic oxidation during leaching, and (3) evaluation of methods for contacting the HEPA solids with the leaching solution and for separating the solid residue from the leaching liquor. Anodic oxidation of Ce(III) was accomplished with an electric current efficiency of about 85% at current densities of 0.04 to… more
Date: May 1, 1980
Creator: Scheitlin, F.M. & Bond, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of high Ni-Cr alloys and Type 304L stainless steel in HNO/sub 3/-HF

Description: Nineteen alloys were evaluated as possible materials of construction for steam heating coils, the dissolver vessel, and the off-gas system of proposed facilities to process thorium and uranium fuels. Commercially available alloys were found that are satisfactory for all applications. With thorium fuel, which requires HNO/sub 3/-HF for dissolution, the best alloy for service at 130/sup 0/C when complexing agents for fluoride are used is Inconel 690; with no complexing agents at 130/sup 0/C, Inco… more
Date: April 1, 1980
Creator: Ondrejcin, R.S. & McLaughlin, B.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quality engineering and control. Semiannual progress report, November-December 1978, January-April 1979. [PCB]

Description: This document reports the following: atomic absorption spectroscopy of Ir in Pu-Ir alloys; removal of Pu from soil; surface microanalysis using elemental x-ray mapping; microscopic scanning of Ga in Pu; microscopy of defects in Pu; emission spectroscopy of Ir and Y in PuO/sub 2/; gas chromatograhy of PCB's in transformer oils and water; liquid chromatography of chlorophenoxy acid herbicides in water; solution analysis by spark source mass spectrometry; a portable gas sampling system; flamm… more
Date: August 2, 1980
Creator: Carpenter, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vapor-liquid equilibria for nitric acid-water and plutonium nitrate-nitric acid-water solutions

Description: The liquid-vapor equilibrium data for nitric acid and nitric acid-plutnonium nitrate-water solutions were examined to develop correlations covering the range of conditions encountered in nuclear fuel reprocessing. The scanty available data for plutonium nitrate solutions are of poor quality but allow an order of magnitude estimate to be made. A formal thermodynamic analysis was attempted initially but was not successful due to the poor quality of the data as well as the complex chemical equilib… more
Date: January 1, 1980
Creator: Maimoni, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scrubbing of iodine from gas streams with mercuric nitrate-conversion of mercuric iodate product to barium iodate for fixation in concrete

Description: A bench-scale model of a mercuric nitrate scrubber for removal of iodine from off-gas streams was constructed and operated in conjunction with a mercuric iodate-to-barium iodate conversion system to determine the feasibility of total recycle of all processing solutions. The two main aspects of the system examined were (1) the extent of contamination of the barium iodate product, and (2) the effect of cross-contamination of various process solutions on the efficiency of the process. The experime… more
Date: June 1, 1980
Creator: Rogers, G. C.; Moore, J. G. & Morgan, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Removal of hazardous radionuclides from uranium ore and/or mill tailings. Progress report, October 1, 1978-September 30, 1979

Description: The leaching of uranium ore and mill tailings to remove radium was studied. A few scouting tests were performed to obtain data on the recovery of radium, thorium, and uranium from leach liquors and on the recycle of leaching agents. Nitric acid, hydrochloric acid, ethylenediaminetetraacetic acid (EDTA), and diethylenetriaminepentaacetic acid (DTPA) were evaluated as leachants using one sample of a western US ore and two samples of tailings obtained from different uranium mills that employ the s… more
Date: January 1, 1980
Creator: Scheitlin, F.M. & Bond, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory studies on the evolution of iodine-129 during Purex-uranium metal dissolution

Description: The path of iodine from the Purex dissolver was determined during fuel dissolution using /sup 125/I tracer. Laboratory-scale equipment qualification studies were completed using sections of nonirradiated uranium N-reactor fuel elements. A proof-of-principle dissolution study was completed at the end of FY 1979 in the PNL hot cells using wafers of irradiated N-reactor fuel. The findings include the following: the laboratory-scale dissolver/downdraft condenser was designed at a factor of 5 x 10/s… more
Date: March 1, 1980
Creator: Bray, L.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization and quantification of the oxides of sulfur and nitrogen and associated compounds in their gaseous, aerosol, and dissolved states

Description: The needs and problems associated with the characterization and quantification of the oxides of sulfur and nitrogen and associated compounds in their gaseous, aerosol, and dissolved states are discussed. Illustrations are given of the techniques in present usage for the determination of the substances of interest to investigators concerned with the effects of air pollutants on the terrestrial ecosystem. The value and utility of the newer techniques employing real time continuous instrumentation… more
Date: May 1, 1980
Creator: Newman, L
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Operation of the radioactive acid digestion test unit

Description: The Radioactive Acid Digestion Test Unit (RADTU) has been constructed at Hanford to demonstrate the application of the Acid Digestion Process for treating combustible transuranic wastes and scrap materials. The RADTU with its original tray digestion vessel has recently completed a six-month campaign processing potentially contaminated nonglovebox wastes from a Hanford plutonium facility. During this campaign, it processed 2100 kg of largely cellulosic wastes at an average sustained processing r… more
Date: January 1, 1980
Creator: Blasewitz, A. G.; Allen, C. R.; Lerch, R. E.; Ely, P. C. & Richardson, G. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plutonium recovery at the Los Alamos Scientific Laboratory

Description: Research programs have led to the adoption of procedures for all phases of plutonium recovery and purification. This report discusses some of the many procedures required to recover and purify the plutonium contained in the residues generated by LASL research, process development, and production activities. The report also discusses general plant facilities, the liquid and gaseous effluents, and solid waste management practices at the New Plutonium Facility, TA-55. Many of the processes or oper… more
Date: June 1, 1980
Creator: Christensen, E.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Studies of the dissolution of geothermal scale

Description: Samples of geothermal scale formed from Magmamax No. 1 and Woolsey No. 1 wells in the Imperial Valley, Calif., were exposed to concentrated and dilute solutions of common laboratory reagents. The time of exposure and temperature of the reagent were also varied. Several reagents easily dissolved significant amounts of the scale. An in situ test was performed with marginal success.
Date: February 4, 1980
Creator: Deutscher, S.B.; Ross, D.M.; Quong, R. & Harrar, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Volatility of ruthenium-106, technetium-99, and iodine-129, and the evolution of nitrogen oxide compounds during the calcination of high-level, radioactive nitric acid waste

Description: The nitrate anion is the predominant constituent in all high-level nuclear wastes. Formic acid reacts with the nitrate anion to yield noncondensable, inert gases (N/sub 2/ or N/sub 2/O), which can be scrubbed free of /sup 106/Ru, /sup 129/I, and /sup 99/Tc radioactivities prior to elimination from the plant by passing through HEPA filters. Treatment of a high-level authentic radioactive waste with two moles of formic acid per mole of nitrate anion leads to a low RuO/sub 4/ volatility of about 0… more
Date: February 1, 1980
Creator: Rimshaw, S. J.; Case, F. N. & Tompkins, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of LWR environmental control technology performance and cost

Description: This study attempts to establish a ranking for species that are routinely released to the environment for a projected nuclear power growth scenario. Unlike comparisons made to existing standards, which are subject to frequent revision, the ranking of releases can be used to form a more logical basis for identifying the areas where further development of control technology could be required. This report describes projections of releases for several fuel cycle scenarios, identifies areas where al… more
Date: March 1, 1980
Creator: Heeb, C. M.; Aaberg, R. L.; Cole, B. M.; Engel, R. L.; Kennedy, W. E., Jr. & Lewallen, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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X-ray photoemission spectroscopy and ion backscattering analysis of leached simulated waste glass containing UO/sub 3/

Description: UO/sub 3/ has been dissolved into several complex borosilicate glasses including Battelle simulated waste glasses 76-68, 3008, and 76-101. The glass surfaces were examined before and after leaching using x-ray photoemission spectroscopy and backscattered ion beam profiling. Samples leached in distilled water showed enhanced surface layer concentrations of several elements including uranium, titanium, zinc, iron and rare earths. For the case of uranium in 76-101, a simple experiment involving le… more
Date: January 1, 1980
Creator: Karim, D.P. & Lam, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Search for an in-line nitric acid analyzer

Description: A literature search was conducted to identify possible techniques for measuring mineral acid normality in the presence of heavy metal salts, undissolved solids, and high radiation fields. Of the techniques noted, eight were identified that could be applicable to the objective. The possibilities were reduced to two methods, which warrant further investigation. These two are refractometry and a modified coulometric-polarographic method. All methods are discussed in detail followed by rationale fo… more
Date: October 1, 1980
Creator: Gallagher, K. Y. & Johnson, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acid rain: the impact of local sources

Description: It has been assumed that acid rain is predominantly a problem of long-range transport of pollutants from large fossil fuel combustion sources, namely coal-fired utilities. However, close examination of fuel use information and source emission characteristics in the Adirondacks, Florida, and California suggests that local oil burning and automotive sources may be major contributors to the occurrence of acid rain in these areas. This report describes the possible role of local combustion sources … more
Date: November 24, 1980
Creator: Spaite, P.; Esposito, M.P.; Szabo, M.F. & Devitt, T.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of the sealed-reflux dissolution system to 100-gram samples

Description: We adapted the sealed-reflux dissolution system (described in Los Alamos Scientific Laboratory report LA-5576) to dissolve up to 100 g of refractory materials. The simplified pressurized-acid system was enlarged to accommodate a greater volume of acid and refractory materials. The acid and sample materials are heated between 150 and 190/sup 0/C at a pressure of 0.14 to 0.20 MPa (20-29 psi). We also describe a second system for dissolving up to 5 g of refractory materials at 150/sup 0/C and a pr… more
Date: December 1, 1980
Creator: Gonzales de Duval, R. M.; Dahlby, J. W. & Lovell, A. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adhesion and chemical vapor testing of second surface silver/glass solar mirrors

Description: Second surface silvered glass mirrors supplied by four different commercial manufacturers were evaluated for silver-to-glass adhesion and resistance to chemical vapor attack. The mirrors were chemically silvered on identical substrates of low iron float glass. Experiments were performed in order to assess the viability of using adhesion and chemical attack as screening tests for predicting the relative long-term durability of solar mirrors. The results of these tests will be compared at a futur… more
Date: September 1, 1980
Creator: Dake, L.S. & Lind, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Photochemistry and kinetics of gas phase reactions involving HO and Cl radicals

Description: The kinetics of the reaction of the HO radical with HNO/sub 3/ and H/sub 2/O/sub 2/, the kinetics of Cl atom reactions with ClNO and ClNO/sub 2/, and the photochemistry of ClNO/sub 2/ and ClONO/sub 2/ were examined. The ultraviolet absorption cross sections of HNO/sub 3/ and ClNO/sub 2/ were also determined as part of the kinetics work. The rate constant for the reaction of HO with HNO/sub 3/ at room temperature was measured to be (8.2 +- 1.8) x 10/sup -14/ cm/sup 3/ molecule/sup -1/ s/sup -1/,… more
Date: November 1, 1980
Creator: Nelson, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium from HEPA filters by Ce(IV)-promoted dissolution of PuO/sub 2/ and recycle of the cerium promoter

Description: The experimental studies carried out included (1) the electrolytic production of Ce(IV) from Ce(III), (2) the leaching of refractory PuO/sub 2/ from HEPA filter materials with maintenance of Ce(IV) concentrations by anodic oxidation during leaching, and (3) evaluation of methods for contacting the HEPA solids with the leaching solution and for separating the solid residue from the leaching liquor. Anodic oxidation of Ce(III) was accomplished with an electric current efficiency of about 85% at c… more
Date: January 1, 1980
Creator: Leuze, R. E.; Bond, W. D. & Scheitlin, F. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Polymerization of Pu(IV) in aqueous nitric acid solutions

Description: The polymerization of Pu(IV) in aqueous nitric acid solutions has been studied spectrophotometrically both to establish the influence of large UO{sub 2}(NO{sub 3}){sub 2} concentrations on the polymerization rates and, more generally, to review the influence of the major parameters on the polymer reaction. Typically, experiments have been performed at 50{sup 0}C and with 0.05 M Pu in nitric acid solutions that vary in acidity from 0.07 to 0.4 M. An induction period usually precedes the polymer … more
Date: October 1, 1980
Creator: Toth, L.M.; Friedman, H.A. & Osborne, M.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thorex solvent extraction studies with irradiated HTGR fuel: series I

Description: A series of solvent extraction experiments to test the first-cycle fuel reprocessing flowsheet, proposed by the General Atomic Company for the Hot Engineering Test Facility, was completed. Using irradiated fuel, the experiments were designed to test the extraction, partition, partition-scrub, and strip operations. Each experiment utilized crosscurrent batch extractions and consecutive stages. Each stage was tested in duplicate. Experimental procedures were developed with synthetic feeds and the… more
Date: October 1, 1980
Creator: Lamb, C.E.; Mitchell, A.D.; Vaughen, V.C.A. & Shannon, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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