Process for the extraction of technetium from uranium

Gong, Cynthia-May S; Poineau, Frederic; Czerwinski, Kenneth R

Title: Process for the extraction of technetium from uranium

Full Record
Other Related Research

Abstract

A spent fuel reprocessing method contacts an aqueous solution containing Technetium(V) and uranyl with an acidic solution comprising hydroxylamine hydrochloride or acetohydroxamic acid to reduce Tc(V) to Tc(II, and then extracts the uranyl with an organic phase, leaving technetium(II) in aqueous solution.

Inventors:

Gong, Cynthia-May S ^[1]; Poineau, Frederic ^[2]; Czerwinski, Kenneth R ^[2]

San Mateo, CA
Las Vegas, NV

Issue Date:: 2010-12-21

Research Org.:: The Board of Regents of the Nevada System of Higher Education of the University of Nevada, Las Vegas

Sponsoring Org.:: USDOE

OSTI Identifier:: 1009529

Patent Number(s):: 7854907

Application Number:: 12/313,354

Assignee:: The Board of Regents of the Nevada System of Higher Education of the University of Nevada, Las Vegas

Patent Classifications (CPCs):: C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F

C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS

Show more

C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G43/003 - {Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange}
C01G99/003 - {Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange}

C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
C22B61/00 - Obtaining metals not elsewhere provided for in this subclass
C22B7/007 - {by acid leaching}

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C19/46 - Aqueous processes {, e.g. by using organic extraction means, including the regeneration of these means}

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/30 - Nuclear fission reactors

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02P - CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
Y02P10/20 - Process efficiency

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02W - CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
Y02W30/50 - Reuse, recycling or recovery technologies

Show less

DOE Contract Number:: FC07-06ID14781

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Citation Formats


                    Gong, Cynthia-May S, Poineau, Frederic, and Czerwinski, Kenneth R. Process for the extraction of technetium from uranium.  United States: N. p., 2010. 
        Web.

Copy to clipboard


                    Gong, Cynthia-May S, Poineau, Frederic, & Czerwinski, Kenneth R. Process for the extraction of technetium from uranium.  United States.

Copy to clipboard


                    Gong, Cynthia-May S, Poineau, Frederic, and Czerwinski, Kenneth R. Tue .  
        "Process for the extraction of technetium from uranium".  United States.  https://www.osti.gov/servlets/purl/1009529.

Copy to clipboard


                    
@article{osti_1009529,

  title        = {Process for the extraction of technetium from uranium},

  author       = {Gong, Cynthia-May S and Poineau, Frederic and Czerwinski, Kenneth R},

  abstractNote = {A spent fuel reprocessing method contacts an aqueous solution containing Technetium(V) and uranyl with an acidic solution comprising hydroxylamine hydrochloride or acetohydroxamic acid to reduce Tc(V) to Tc(II, and then extracts the uranyl with an organic phase, leaving technetium(II) in aqueous solution.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2010},

  month        = {12}

}

Copy to clipboard

Patent:

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE Patents and OSTI.GOV collections:

Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste

Patent Zaitsev, Boris N [St. Petersburg, RU]; Esimantovskiy, Vyacheslav M [St. Petersburg, RU]; Lazarev, Leonard N [St. Petersburg, RU]; ...

Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extractedmore » « less
Full Text Available
Process for extracting technetium from alkaline solutions

Patent Moyer, Bruce A [Oak Ridge, TN]; Sachleben, Richard A [Knoxville, TN]; Bonnesen, Peter V [Knoxville, TN]

A process for extracting technetium values from an aqueous alkaline solution containing at least one alkali metal hydroxide and at least one alkali metal nitrate, the at least one alkali metal nitrate having a concentration of from about 0.1 to 6 molar. The solution is contacted with a solvent consisting of a crown ether in a diluent for a period of time sufficient to selectively extract the technetium values from the aqueous alkaline solution. The solvent containing the technetium values is separated from the aqueous alkaline solution and the technetium values are stripped from the solvent.
Full Text Available
Removing oxygen from a solvent extractant in an uranium recovery process

Patent Hurst, Fred J [Oak Ridge, TN]; Brown, Gilbert M [Knoxville, TN]; Posey, Franz A [Concord, TN]

An improvement in effecting uranium recovery from phosphoric acid solutions is provided by sparging dissolved oxygen contained in solutions and solvents used in a reductive stripping stage with an effective volume of a nonoxidizing gas before the introduction of the solutions and solvents into the stage. Effective volumes of nonoxidizing gases, selected from the group consisting of argon, carbon dioxide, carbon monoxide, helium, hydrogen, nitrogen, sulfur dioxide, and mixtures thereof, displace oxygen from the solutions and solvents thereby reduce deleterious effects of oxygen such as excessive consumption of elemental or ferrous and accumulation of complex iron phosphates or cruds.
Full Text Available
Reductive stripping process for uranium recovery from organic extracts

Patent Hurst, Jr., Fred J. (Oak Ridge, TN)

In the reductive stripping of uranium from an organic extractant in a uranium recovery process, the use of phosphoric acid having a molarity in the range of 8 to 10 increases the efficiency of the reductive stripping and allows the strip step to operate with lower aqueous to organic recycle ratios and shorter retention time in the mixer stages. Under these operating conditions, less solvent is required in the process, and smaller, less expensive process equipment can be utilized. The high strength H.sub.3 PO.sub.4 is available from the evaporator stage of the process.
Full Text Available
Separation of uranium from technetium in recovery of spent nuclear fuel

Patent Friedman, Horace A [Oak Ridge, TN]

A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.
Full Text Available

Similar Records