1,135 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Nitric Acid"  
Results: 1 - 24 next
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

Phase Transformations in Alumina. Technical Report, May to December 1961

Description: e transformation studies showed that synthetic aluminas produced in the laboratory were not transformed to alpha alumina at 400 to 700' deg n the presence of nitric acid and water vapor. Amorphous aluminn produced in the pilot plant was transformed to alpha alumina. This indicated that the amorphous alumina produced in the pilot plant is structurally predisposed to form alpha alumina. Most additives did not appear to have any special effects. Lithium formed zeta alumina, LiAl/sub 5/O/sub 8/. Ph… more
Date: December 1, 1961
Creator: Eding, H J; Huggins, M L & Brown, A G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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
open access

Simultaneous analysis of uranium and nitrate

Description: A direct spectrophotometric method has been developed for the determination of 20 to 200 g/l of uranium in the presence of 3 to 5 M nitric acid. A dual-wavelength analysis is used to eliminate the enhancing effect of nitrate ion on the uranium visible spectra. The precision and accuracy of the simultaneous analysis of uranium and nitrate were compared using combinations of the four uranium wavelength maxima, occurring at 426, 416, 403 and 359 nm. Calculations based on 426 and 416 nm data yielde… more
Date: April 1, 1978
Creator: Bostick, D.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ceramic and cermet targets

Description: Use of isotopic materials as targets in high temperature environments, e.g., reactor cores, require that chemically stable forms of the isotopes be employed. Usually oxides are compatible with temperatures > 1600/sup 0/K, although some light element oxides exhibit some volatility at temperatures > 1300/sup 0/K. Especially in the case of heavy elements, the relatively low melting points of the metals, poor compatibility of the metals with encapsulation materials, and high chemical reactivity at … more
Date: January 1, 1979
Creator: Kobisk, E. H.; Quinby, T. C. & Aaron, W. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Double liquid membrane system for the removal of actinides and lanthanides from acidic nuclear wastes

Description: Supported liquid membranes (SLM), consisting of an organic solution of n-octyl-(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and tributyl-phosphate (TBP) in decalin are able to perform selective separation and concentration of actinide and lanthanide ions from aqueous nitrate feed solutions and synthetic nuclear wastes. In the membrane process a possible strip solution is a mixture of formic acid and hydroxylammonium formate (HAF). The effectiveness of this strip solution is redu… more
Date: January 1, 1985
Creator: Chiarizia, R. & Danesi, P.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium(IV) hydrous polymer chemistry

Description: The hydrous polymer chemistry of Pu(IV) in aqueous nitric acid solutions has been a subject of considerable interest for several years. This interest stems mainly from the fact that most nuclear fuel reprocessing schemes based on the Purex process can be hampered by the occurrence of polymer. As a result, an understanding and control of the parameters that affect polymer formation during reprocessing are studied. 2 refs.
Date: January 1, 1985
Creator: Toth, L.M. & Dodson, K.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A Modified Pyroelectric Sodium Fluoride Carrier Distillation Medthod For The Spectrographic Analysis Of Impurities In Plutonium

Description: A modification of the pyroelectric sodium fluoride carrier distillation method for analysis of impurities in plutonium metal is described. The metal is dissolved. Plutonium is precipitated and treated with nitric acid. The slurry obtained is dried and ignited. The resultant low density oxide is mixed with sodium fluoride and pressed into a pellet for arcing. Cobalt is used as the internal standard for densitometric using visual comparisons against prepared standards. The procedural modification… more
Date: August 1, 1966
Creator: Schreiber, G. A. & Barrick, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Method for cleaning solution used in nuclear-fuel reprocessing.

Description: A nuclear fuel processing solution containing: (1) hydrocarbon diluent; (2) tri-n-butyl phosphate or tri-2-ethylhexyl phosphate; and (3) monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, di-2-ethylhexyl phosphate, or a complex formed by plutonium, uranium, or a fission product thereof with monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, or di-2-ethylhexyl phosphate is contacted with silica gel having alkali ions absorbed thereon to remove any degradation … more
Date: May 12, 1981
Creator: Tallent, O. K.; Dodson, K. E. & Mailen, J. C.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
open access

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
open access

Decontamination processes for waste glass canisters

Description: The process which will be used to decontaminate waste glass canisters at the Savannah River Plant consists of: decontamination (slurry blasting); rinse (high-pressure water); and spot decontamination (high-pressure water plus slurry). No additional waste will be produced by this process because glass frit used in decontamination will be mixed with the radioactive waste and fed into the glass melter. Decontamination of waste glass canisters with chemical and abrasive blasting techniques was inve… more
Date: June 1, 1981
Creator: Rankin, W.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
open access

Kilogram-scale purification of americium by ion exchange

Description: Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of… more
Date: January 1, 1979
Creator: Wheelwright, E. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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
open access

Solvent extraction of thorium from nitrate solutions by dibutyl butylphosphonate in Isopar H

Description: Solvent extraction of thorium by 30 vol % dibutyl butylphosphonate-70 vol % Isopar H from salted and nonsalted nitric acid solutions was studied. Thorium distribution coefficients D/sub Th/'s were obtained for nitric acid solutions of approx. 0.3 to approx. 12 N and for solutions of 1 and 2 M NH/sub 4/NO/sub 3/ over the HNO/sub 3/ concentration range of approx. 0.5 to approx. 9 N. The nitric acid solution D/sub Th/'s varied from approx. 4.3 at the lowest acidity, increased to a maximum of appro… more
Date: January 1, 1982
Creator: Freer, J.E.; Crump, D.H.; Axler, K.M.; Clifton, D.G.; S.W., Hayter & Mills, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Back to Top of Screen