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Journal of Nuclear Medicine

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Meeting ReportMolecular Targeting Probes - Radioactive and Nonradioactive

Separation of TcO4- and MoO42- using a PEG coated C18 SPE cartridge

Jan Andersson, John Wilson, Katherine Gagnon, Joseph Romaniuk, Alexander McEwan, Douglas Abrams and Steve McQuarrie
Journal of Nuclear Medicine May 2013, 54 (supplement 2) 1001;
Jan Andersson
1University of Alberta, Edmonton, AB, Canada
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John Wilson
1University of Alberta, Edmonton, AB, Canada
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Katherine Gagnon
1University of Alberta, Edmonton, AB, Canada
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Joseph Romaniuk
1University of Alberta, Edmonton, AB, Canada
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Alexander McEwan
1University of Alberta, Edmonton, AB, Canada
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Douglas Abrams
1University of Alberta, Edmonton, AB, Canada
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Steve McQuarrie
1University of Alberta, Edmonton, AB, Canada
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Abstract

1001

Objectives A critical aspect in the feasibility of routine cyclotron production of 99mTc via the 100Mo(p,2n)99mTc reaction is the separation of 99mTc from the bulk 100Mo target. The aim of this work was to assess if polyethylene glycol (PEG) coated on commercially available solid phase extraction (SPE) cartridges can be a viable method for the separation of pertechnetate (TcO4-) from molybdate (MoO42-). The recovered [99mTc]TcO4- purity and the recovered MoO42- yield for possible recycling was evaluated.

Methods Separations were performed on an automated chemistry unit. C18 cartridges containing 3 g of resin were coated by pouring PEG3000 solution through the cartridge and then washing with deionized water (D.I. H2O). PEG concentration in the final product was evaluated by iodine visualization TLC. Initial separation testing was performed using generator eluted [99mTc]TcO4- and [99Mo]MoO42- in a loading solution containing 300 mg Mo powder dissolved in 10 mL H2O2 and 10 mL (NH4)2CO3 (3 M). After loading, the column was washed with 5 mL (NH4)2CO3 (1 M) followed by 1.5 mL D.I. H2O. The [99mTc]TcO4- was eluted using 10 mL D.I. H2O and passed through a strong cation exchange column and an alumina column. The [99mTc]TcO4- was eluted from the alumina column using 10 mL of isotonic saline.

Results Recovery of 99mTc was 92 ± 4 % (n=4). Greater than 99.5 % of the 99Mo was present in the load/wash fractions (n=2) thus allowing for minimal losses in terms of recycling enriched 100Mo. PEG3000 concentration in the final product was lower than the limit of detection for our TLC spot test (0.1 mg/mL), pH was 6 and the product was clear and colorless

Conclusions We developed a practical and easily accessible system for separation of 99mTc-pertechnetate, with good recovery yields for [99mTc]TcO4- and promising features for molybdenum recovery. The final product passed appropriate QC tests.

Research Support This work was supported by research grants from NSERC/CIHR and Natural Resources Canada.

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Journal of Nuclear Medicine
Vol. 54, Issue supplement 2
May 2013
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Separation of TcO4- and MoO42- using a PEG coated C18 SPE cartridge
Jan Andersson, John Wilson, Katherine Gagnon, Joseph Romaniuk, Alexander McEwan, Douglas Abrams, Steve McQuarrie
Journal of Nuclear Medicine May 2013, 54 (supplement 2) 1001;

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Separation of TcO4- and MoO42- using a PEG coated C18 SPE cartridge
Jan Andersson, John Wilson, Katherine Gagnon, Joseph Romaniuk, Alexander McEwan, Douglas Abrams, Steve McQuarrie
Journal of Nuclear Medicine May 2013, 54 (supplement 2) 1001;
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