Process for radioisotope recovery and system for implementing same

Meikrantz, David H; Todd, Terry A; Tranter, Troy J; Horwitz, E Philip

Title: Process for radioisotope recovery and system for implementing same

Abstract

A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.

Inventors:

Meikrantz, David H ^[1]; Todd, Terry A ^[2]; Tranter, Troy J ^[1]; Horwitz, E Philip ^[3]

Idaho Falls, ID
Aberdeen, ID
Naperville, IL

Issue Date:: 2009-10-06

Research Org.:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1003002

Patent Number(s):: 7597862

Application Number:: 11/533,592

Assignee:: Battelle Energy Alliance, LLC (Idaho Falls, ID)

Patent Classifications (CPCs):: C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS

G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS

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C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
C22B30/06 - Obtaining bismuth
C22B60/00 - Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
C22B60/0295 - {obtaining other actinides except plutonium}

G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
G21G4/00 - Radioactive sources

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

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DOE Contract Number:: AC07-99ID13727

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY

Citation Formats


                    Meikrantz, David H, Todd, Terry A, Tranter, Troy J, and Horwitz, E Philip. Process for radioisotope recovery and system for implementing same.  United States: N. p., 2009. 
        Web.

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                    Meikrantz, David H, Todd, Terry A, Tranter, Troy J, & Horwitz, E Philip. Process for radioisotope recovery and system for implementing same.  United States.

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                    Meikrantz, David H, Todd, Terry A, Tranter, Troy J, and Horwitz, E Philip. Tue .  
        "Process for radioisotope recovery and system for implementing same".  United States.  https://www.osti.gov/servlets/purl/1003002.

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@article{osti_1003002,

  title        = {Process for radioisotope recovery and system for implementing same},

  author       = {Meikrantz, David H and Todd, Terry A and Tranter, Troy J and Horwitz, E Philip},

  abstractNote = {A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2009},

  month        = {10}

}

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Works referenced in this record:

An improved extraction chromatographic resin for the separation of uranium from acidic nitrate media
journal, July 2001

Dietz, M.
Talanta, Vol. 54, Issue 6
https://doi.org/10.1016/S0039-9140(01)00390-3

Production of actinium-225 for alpha particle mediated radioimmunotherapy
journal, May 2005

Boll, Rose A.; Malkemus, Dairin; Mirzadeh, Saed
Applied Radiation and Isotopes, Vol. 62, Issue 5
https://doi.org/10.1016/j.apradiso.2004.12.003

Novel Extraction of Chromatographic Resins Based on Tetraalkyldiglycolamides: Characterization and Potential Applications
journal, May 2005

Horwitz, E. P.; McAlister, D. R.; Bond, A. H.
Solvent Extraction and Ion Exchange, Vol. 23, Issue 3
https://doi.org/10.1081/SEI-200049898

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Title: Process for radioisotope recovery and system for implementing same

Abstract

Citation Formats

An improved extraction chromatographic resin for the separation of uranium from acidic nitrate media journal, July 2001

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Novel Extraction of Chromatographic Resins Based on Tetraalkyldiglycolamides: Characterization and Potential Applications journal, May 2005

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