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in subjects: "Butyl Phosphates"

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

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Calculated and experimental studies of nonequilibrium solvent extraction of uranium-thorium and uranium-zirconium

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: Article

Partner: UNT Libraries Government Documents Department

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Ferrocyanide-containing waste tanks: Ferrocyanide chemistry and reactivity

The complexing constant for hexacyano-iron complexes, both Fe(2) and Fe(3), are exceptionally large. The derived transition metal salts or double salts containing alkali metal ions are only slightly soluble. The various nickel compounds examined in this study, i.e., those predicted to have been formed in the Hanford waste scavenging program, are typical examples. In spite of their relative stability towards most reagents under ambient conditions, they are all thermodynamically unstable towards … more

Date: September 1, 1991

Creator: Scheele, R. D.; Burger, L. L.; Tingey, J. M.; Bryan, S. A.; Borsheim, G. L.; Simpson, B. C. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Consolidated fuel-reprocessing program. Progress report, April 1-June 30, 1982

Highlights of progress accomplished during the quarter ending June 30, 1982 are summarized. Discussion is presented under the headings: Process development; Laboratory R and D; Engineering research; Engineering systems; Integrated equipment test facility operation; Instrument development; and HTGR fuel reprocessing.

Date: September 1, 1982

Creator: Burch, W D

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Fluidized bed incineration of transuranic contaminated waste

A 9 kg/h pilot scale fluidized bed incinerator is now being used for burning various types of radioactive waste at Rocky Flats Plant. General solid combustible waste containing halogenated materials is burned in a fluidized bed of sodium carbonate for in stu neutralization of thermally generated acidic gases. A variety of other production related materials has been burned in the incinerator, including ion exchange resin, tributyl phosphate solutions, and air filters. Successful operation of the… more

Date: January 1, 1976

Creator: Ziegler, D. L. & Johnson, A. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

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: Article

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

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: Report

Partner: UNT Libraries Government Documents Department

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Droplet size characteristics and energy input requirements of emulsions formed using high-intensity-pulsed electric fields

Experimental methods have been developed to measure droplet size characteristics and energy inputs associated with the rupture of aqueous droplets by high-intensity-pulsed electric fields. The combination of in situ microscope optics and high-speed video cameras allows reliable observation of liquid droplets down to 0.5 ..mu..m in size. Videotapes of electric-field-created emulsions reveal that average droplet sizes of less than 5 ..mu..m are easily obtained in such systems. Analysis of the ene… more

Date: January 1, 1987

Creator: Scott, T.C. & Sisson, W.G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Status report: waste incineration and fixation for Waste Management, Production, and Reprocessing Division of the Department of Energy (July--December 1976)

Fluidized bed incineration and waste fixation processes are being used to process the types of wastes expected from nuclear fuel reprocessing and production plants. Test incineration runs have been made on two types of wastes: high efficiency particulate air (HEPA) filters and tributyl phosphate-solvent solutions. Laboratory-scale vitrification equipment was used to produce glass pellets from incinerator ash and blends of other expected waste streams. Computer modeling gave an expected product … more

Date: November 25, 1977

Creator: Ziegler, D. L.; White, J. W.; Johnson, A. J.; Fong, L. Q.; Teter, A. R. & Chung, S. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Method for cleaning solution used in nuclear-fuel reprocessing.

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: Patent

Partner: UNT Libraries Government Documents Department

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Trace elements retained in washed nuclear fuel reprocessing solvents

Analysis of purified TBP extractant from solvent extraction processes at Savannah River Plant showed several stable elements and several long-lived radioisotopes. Stable elements Al, Na, Br, Ce, Hg, and Sm are found in trace quantities in the solvent. The only stable metallic element consistently found in the solvent was Al, with a concentration which varies from about 30 ppM to about 10 ppM. The halogens Br and Cl appear to be found in the solvent systems as organo halides. Radionuclides found… more

Date: September 1, 1979

Creator: Gray, L.W. & MacMurdo, K.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels

Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need for an efficient feed clarification. A potentially useful filtration method for fulfilling this need has been demonstrated. Conditions necessary for the satisfactory use of unstabilized hydroxylamine nitrate (HAN) or nitrous acid as the reducing agent for Pu(IV) during reductive stripping operations have been defined. Both partial partitioning and total costripping operations have been demonstrate… more

Date: January 1, 1982

Creator: Collins, E. D.; Benker, D. E.; Bigelow, J. E.; Chattin, F. R.; King, L. J.; Lloyd, M. H. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Silver-catalyzed PuO sub 2 dissolution with persulfate

This report consists of 14 slides and associated narrative for a presentation to be given at the 15th Annual Actinide Separations Conference on silver-catalyzed PuO{sub 2} dissolution with persulfate. (JL)

Date: June 1, 1991

Creator: Fisher, F D; Barney, G S; Cooper, T D & Duchsherer, M J

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Purex diluent degradation

The chemical degradation of normal paraffin hydrocarbon (NPH) diluents both in the pure state and mixed with 30% tributyl phosphate (TBP) was investigated in a series of experiments. The results show that degradation of NPH in the TBP-NPH-HNO/sub 3/ system is consistent with the active chemical agent being a radical-like nitrogen dioxide (NO/sub 2/) molecule, not HNO/sub 3/ as such. Spectrophotometric, gas chromatographic, mass spectrographic, and titrimetric methods were used to identify the d… more

Date: February 1, 1984

Creator: Tallent, O. K.; Mailen, J. C. & Pannell, K. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Secondary cleanup of Idaho Chemical Processing Plant solvent

Solvent from the Idaho Chemical Processing Plant (ICPP) (operated by Westinghouse Idaho Nuclear Company, Inc.) has been tested to determine the ability of activated alumina to remove secondary degradation products - those degradation products which are not removed by scrubbing with sodium carbonate.

Date: January 1, 1985

Creator: Mailen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Purex: process and equipment performance

The Purex process is the solvent extraction system that uses tributyl phosphate as the extractant for separating uranium and plutonium from irradiated reactor fuels. Since the first flowsheet was proposed at Oak Ridge National Laboratory in 1950, the process has endured for over 30 years with only minor modifications. The spread of the technology was rapid, and worldwide use or research on Purex-type processes was reported by the time of the 1955 Geneva Conference. The overall performance of th… more

Date: January 1, 1986

Creator: Orth, D.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Purex process solvent: literature review

This document summarizes the data on Purex process solvent presently published in a variety of sources. Extracts from these various sources are presented herein and contain the work done, the salient results obtained, and the original, unaltered conclusions of the author of each paper. Three major areas are addressed: solvent stability, solvent quality testing, and solvent treatment processes. 34 references, 44 tables.

Date: October 1, 1979

Creator: Geier, R. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CC1/sub 4/ process solvent

The stability of the TRUEX-CCl/sub 4/ solvent (0.25M OphiD(iB)CMPO-0.75M TBP-CCl/sub 4/) toward hydrolytic and gamma-radiolytic degration is presently under study. The experimental procedure is discussed. Reported this quarter are the complete results for experiments run at 50/sup 0/C to measure the nitric-acid-catalyzed degradation of the TRUEX-CCl/sub 4/ solvent and the partial results for hydrolytic degradation experiments run at 70/sup 0/C and gamma-radiolytic degradation experiments run at… more

Date: May 1, 1985

Creator: Vandegrift, G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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THE USE OF VAPOR EXTRACTION SYSTEM AND ITS SUBSEQUENT REDUCTION OF WORKER EXPOSURE TO CARBON TETRACHLORIDE DURING RETRIEVAL OF HANFORDS LEGACY WASTE

The Hanford Site is a decommissioned nuclear productions complex located in south eastern Washington and is operated by the Department of Energy (DOE). From 1955 to 1973, carbon tetrachloride (CCl{sub 4}), used in mixtures with other organic compounds, was used to recover plutonium from aqueous streams at Z Plant located on the Hanford Site. The aqueous and organic liquid waste that remained at the end of this process was discharged to soil columns in waste cribs located near Z Plant. Included … more

Date: March 18, 2008

Creator: DA, PITTS

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Modeling the effect of temperature on thorium and nitric acid extraction and the formation of third phase for modification of the SEPHIS: Thorex computer program

Mathematical models have been developed for use with the SEPHIS - Thorex code which correct for the effect of temperature on thorium and nitric acid extraction and which provide a signal to indicate the formation of a second organic phase. Experimental programs have provided data which have been analyzed and indicate that increasing temperature decreases the distribution coefficient of thorium. Also increasing the temperature increases the concentration of thorium in the organic phase at which … more

Date: May 1, 1979

Creator: Watson, S.B. & Rainey, R.H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Recovery of uranium from 30 vol % tributyl phosphate solvents containing dibutyl phosphate

A number of solid sorbents were tested for the removal of uranium and dibutyl phosphate (DBP) from 30% tributyl phosphate (TBP) solvent. The desired clean uranium product can be obtained either by removing the DBP, leaving the uranium in the solvent for subsequent stripping, or by removing the uranium, leaving the DBP in the solvent for subsequent treatment. The tests performed show that it is relatively easy to preferentially remove uranium from solvents containing uranium and DBP, but quite d… more

Date: January 1, 1986

Creator: Mailen, J. C. & Tallent, O. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Determination of cadmium in solutions containing uranium, neptunium, and plutonium

An analytical method was developed for determining cadmium in solutions containing fissionable materials and high alpha activities. The solutions were first extracted with 30% tributyl phosphate in dodecane to separate the actinide elements from the cadmium. This extraction step removed interfering ions and reduced the alpha activity. The cadmium concentrations were determined by atomic absorption analysis. The method has been applied to solutions containing 20 to 30 g Cd/liter, about 10 g Pu/l… more

Date: February 1, 1979

Creator: Gray, L.W.; Overman, L.A. & Hodgens, H.F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent

The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C/sub 12/-C/sub 14/). The feed solution was 1.0 M in HNO/sub 3/, … more

Date: January 1, 1984

Creator: Horwitz, E. P.; Kalina, D. G.; Diamond, H.; Kaplan, L.; Vandegrift, G. F.; Leonard, R. A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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X-ray-diffraction studies of the structures of organic-phase solvent-extraction complexes

Structures were determined of the complexes which form when the uranyl ion is extracted from nitric acid solutions with organophosphorus reagents: UO/sub 2/(TBPO)/sub 2/(NO/sub 3/)/sub 2/, UO/sub 2/(TiBP)/sub 2/(NO/sub 3/)/sub 2/, UO/sub 2/(DBP)/sub 2/, and UO/sub 2/(DBP)(TBPO)NO/sub 3/. (TiBP = tri-isobutyl phosphate.) (DLC)

Date: January 1, 1983

Creator: Burns, J. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department