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U.S. Department of Energy
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Actinium radioisotope products of enhanced purity

Patent ·
OSTI ID:1176357
A product includes actinium-225 (.sup.225Ac) and less than about 1 microgram (.mu.g) of iron (Fe) per millicurie (mCi) of actinium-225. The product may have a radioisotopic purity of greater than about 99.99 atomic percent (at %) actinium-225 and daughter isotopes of actinium-225, and may be formed by a method that includes providing a radioisotope mixture solution comprising at least one of uranium-233 (.sup.233U) and thorium-229 (.sup.229Th), extracting the at least one of uranium-233 and thorium-229 into an organic phase, substantially continuously contacting the organic phase with an aqueous phase, substantially continuously extracting actinium-225 into the aqueous phase, and purifying the actinium-225 from the aqueous phase. In some embodiments, the product may include less than about 1 nanogram (ng) of iron per millicurie (mCi) of actinium-225, and may include less than about 1 microgram (.mu.g) each of magnesium (Mg), Chromium (Cr), and manganese (Mn) per millicurie (mCi) of actinium-225.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC07-05ID14517
Assignee:
Battelle Energy Alliance, LLC (Idaho Falls, ID)
Patent Number(s):
7,736,610
Application Number:
11/278,522
OSTI ID:
1176357
Country of Publication:
United States
Language:
English

References (7)

An improved extraction chromatographic resin for the separation of uranium from acidic nitrate media journal July 2001
Improvements in Thorium-Uranium Separation in the Acid-Thorex Process book April 1980
Production of actinium-225 for alpha particle mediated radioimmunotherapy journal May 2005
Demonstration of the Potential for Designing Extractants with Preselected Extraction Properties: Possible Application to Reactor Fuel Reprocessing book April 1980
Novel Extraction of Chromatographic Resins Based on Tetraalkyldiglycolamides: Characterization and Potential Applications journal May 2005
The Extraction of DBP and MBP from Actinides: Application to the Recovery of Actinides from TBP-Sodium Carbonate Scrub Solution book April 1980
Heavy Element Separation for Thorium-Uranium-Plutonium Fuels book April 1980

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