High efficiency production and purification of 86Y based on electrochemical separation

Dragoljub Lukić; Claire Tamburella; Franz Buchegger; Gerd Jürgen Beyer; Jožef J. Čomor; Yann Seimbille

doi:10.1016/j.apradiso.2008.12.008

High efficiency production and purification of ⁸⁶Y based on electrochemical separation

Dragoljub Lukić, Claire Tamburella, Franz Buchegger, Gerd Jürgen Beyer, Jožef J. Čomor, Yann Seimbille^*

^*Corresponding author for this work

Research output: Contribution to journal › Article › Academic › peer-review

32 Citations (Scopus)

Abstract

As an intermediate half-life positron emitter ⁸⁶Y is an attractive radioisotope for positron emission tomography (PET) studies, particularly for patient specific dosimetry planning of ⁹⁰Y-based radiotherapy procedures. It can be conveniently produced by a small-sized cyclotron via the ⁸⁶Sr(p,n)⁸⁶Y nuclear reaction. The optimization of the electrochemical separation of ⁸⁶Y from the target material and its purification was done by modeling the whole production cycle using ⁹⁰Y. The radionuclide was isolated using four electrodes in two electrolytic steps. In the first step two Pt plate anodes and a Pt Winkler cathode were used and the electro-deposition yield was determined in constant current mode of operation. In addition, the influence of pH on the efficiency of this first step was investigated. The second electrolysis, with Winkler electrode as anode and a Pt wire as cathode, was also performed in constant current mode of operation. The kinetics of recovery of the deposited activity on the Pt wire was investigated in acidic solutions. The optimized electrochemical method was then applied for ⁸⁶Y separation and purification. This modified procedure was proved to be faster and simpler than the previously proposed electrochemical techniques and is more convenient for automation of the routine production of ⁸⁶Y.

Original language	English
Pages (from-to)	523-529
Number of pages	7
Journal	Applied Radiation and Isotopes
Volume	67
Issue number	4
DOIs	https://doi.org/10.1016/j.apradiso.2008.12.008
Publication status	Published - Apr 2009
Externally published	Yes

Bibliographical note

Funding Information:
This work has been carried out within the Scientific Co-operation between Eastern Europe and Switzerland (SCOPES 2005–2008), Co-operation Agreement no. IB7420-111017. Partial further support by the Geneva Cancer League, Grant no. 313, by the Research and Development Found of Geneva University Hospital and by the Ministry of Science of Serbia is also acknowledged. The authors are thankful to Mr. Michel Pelletier, Department of Inorganic and Analytical Chemistry, University of Geneva, Switzerland, for providing measurements of strontium content.

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10.1016/j.apradiso.2008.12.008

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title = "High efficiency production and purification of 86Y based on electrochemical separation",

abstract = "As an intermediate half-life positron emitter 86Y is an attractive radioisotope for positron emission tomography (PET) studies, particularly for patient specific dosimetry planning of 90Y-based radiotherapy procedures. It can be conveniently produced by a small-sized cyclotron via the 86Sr(p,n)86Y nuclear reaction. The optimization of the electrochemical separation of 86Y from the target material and its purification was done by modeling the whole production cycle using 90Y. The radionuclide was isolated using four electrodes in two electrolytic steps. In the first step two Pt plate anodes and a Pt Winkler cathode were used and the electro-deposition yield was determined in constant current mode of operation. In addition, the influence of pH on the efficiency of this first step was investigated. The second electrolysis, with Winkler electrode as anode and a Pt wire as cathode, was also performed in constant current mode of operation. The kinetics of recovery of the deposited activity on the Pt wire was investigated in acidic solutions. The optimized electrochemical method was then applied for 86Y separation and purification. This modified procedure was proved to be faster and simpler than the previously proposed electrochemical techniques and is more convenient for automation of the routine production of 86Y.",

author = "Dragoljub Luki{\'c} and Claire Tamburella and Franz Buchegger and Beyer, {Gerd J{\"u}rgen} and {\v C}omor, {Jo{\v z}ef J.} and Yann Seimbille",

note = "Funding Information: This work has been carried out within the Scientific Co-operation between Eastern Europe and Switzerland (SCOPES 2005–2008), Co-operation Agreement no. IB7420-111017. Partial further support by the Geneva Cancer League, Grant no. 313, by the Research and Development Found of Geneva University Hospital and by the Ministry of Science of Serbia is also acknowledged. The authors are thankful to Mr. Michel Pelletier, Department of Inorganic and Analytical Chemistry, University of Geneva, Switzerland, for providing measurements of strontium content.",

year = "2009",

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doi = "10.1016/j.apradiso.2008.12.008",

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AU - Lukić, Dragoljub

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AU - Buchegger, Franz

AU - Beyer, Gerd Jürgen

AU - Čomor, Jožef J.

AU - Seimbille, Yann

N1 - Funding Information: This work has been carried out within the Scientific Co-operation between Eastern Europe and Switzerland (SCOPES 2005–2008), Co-operation Agreement no. IB7420-111017. Partial further support by the Geneva Cancer League, Grant no. 313, by the Research and Development Found of Geneva University Hospital and by the Ministry of Science of Serbia is also acknowledged. The authors are thankful to Mr. Michel Pelletier, Department of Inorganic and Analytical Chemistry, University of Geneva, Switzerland, for providing measurements of strontium content.

PY - 2009/4

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N2 - As an intermediate half-life positron emitter 86Y is an attractive radioisotope for positron emission tomography (PET) studies, particularly for patient specific dosimetry planning of 90Y-based radiotherapy procedures. It can be conveniently produced by a small-sized cyclotron via the 86Sr(p,n)86Y nuclear reaction. The optimization of the electrochemical separation of 86Y from the target material and its purification was done by modeling the whole production cycle using 90Y. The radionuclide was isolated using four electrodes in two electrolytic steps. In the first step two Pt plate anodes and a Pt Winkler cathode were used and the electro-deposition yield was determined in constant current mode of operation. In addition, the influence of pH on the efficiency of this first step was investigated. The second electrolysis, with Winkler electrode as anode and a Pt wire as cathode, was also performed in constant current mode of operation. The kinetics of recovery of the deposited activity on the Pt wire was investigated in acidic solutions. The optimized electrochemical method was then applied for 86Y separation and purification. This modified procedure was proved to be faster and simpler than the previously proposed electrochemical techniques and is more convenient for automation of the routine production of 86Y.

AB - As an intermediate half-life positron emitter 86Y is an attractive radioisotope for positron emission tomography (PET) studies, particularly for patient specific dosimetry planning of 90Y-based radiotherapy procedures. It can be conveniently produced by a small-sized cyclotron via the 86Sr(p,n)86Y nuclear reaction. The optimization of the electrochemical separation of 86Y from the target material and its purification was done by modeling the whole production cycle using 90Y. The radionuclide was isolated using four electrodes in two electrolytic steps. In the first step two Pt plate anodes and a Pt Winkler cathode were used and the electro-deposition yield was determined in constant current mode of operation. In addition, the influence of pH on the efficiency of this first step was investigated. The second electrolysis, with Winkler electrode as anode and a Pt wire as cathode, was also performed in constant current mode of operation. The kinetics of recovery of the deposited activity on the Pt wire was investigated in acidic solutions. The optimized electrochemical method was then applied for 86Y separation and purification. This modified procedure was proved to be faster and simpler than the previously proposed electrochemical techniques and is more convenient for automation of the routine production of 86Y.

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ER -

High efficiency production and purification of ⁸⁶Y based on electrochemical separation

Abstract

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