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Improved small scale production of iodine-124 for radiolabeling and clinical applications.

Authors :
Lamparter D
Hallmann B
Hänscheid H
Boschi F
Malinconico M
Samnick S
Source :
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine [Appl Radiat Isot] 2018 Oct; Vol. 140, pp. 24-28. Date of Electronic Publication: 2018 Jun 18.
Publication Year :
2018

Abstract

Aim: This work describes a small-scale production of iodine-124 using a 16.5 MeV cyclotron, and a subsequent validation of the formulated sodium [124I]iodide solution for routinely clinical applications.<br />Methods: Iodine-124 ( <superscript>124</superscript> I) was produced via the <superscript>124</superscript> Te(p, n) <superscript>124</superscript> I reaction using a 16.5 MeV GE PETtrace® cyclotron. Irradiation was performed with a pre-prepared solid target consisting of [ <superscript>124</superscript> Te]TeO <subscript>2</subscript> (99.93%) and Al <subscript>2</subscript> O <subscript>3</subscript> . Different layer thicknesses, irradiation and extraction parameters were tested. After irradiation at the cyclotron, the shuttle with irradiated material was transferred fully automatically via a tube system to the Comecer ALCEO <superscript>®</superscript> Halogen 2.0 extraction unit. Iodine-124 was subsequently extracted in form of sodium [ <superscript>124</superscript> I]iodide ([ <superscript>124</superscript> I]NaI) in 0.05 N aqueous NaOH solution, followed by reconstitution and validation for preclinical and clinical uses.<br />Results: Good result was achieved using a beam degradation foil of 500 µm thickness in combination with beam currents between 10 and 15 µA. Under these conditions, up to 150 MBq no-carrier-added [ <superscript>124</superscript> I]NaI was obtained after a 2 h irradiation time in less than 500 µl 0.05 N NaOH. Isolation of [ <superscript>124</superscript> I]NaI, including evaporation and extraction at the ALCEO <superscript>®</superscript> Halogen EVP unit was accomplished in 90 min 24 h after production (irradiation), the amount of iodine-123 as assessed by gamma-ray spectroscopy was less than 1.5%. The undesirable iodine-125 was not detectable by gamma spectroscopy. The extracted [ <superscript>124</superscript> I]NaI could be used directly for radiolabeling purposes, and after buffering with phosphate buffered saline (PBS) and sterile filtration for clinical applications.<br />Conclusions: Through the optimized conditions for irradiation and extraction, iodine-124 was produced in good radiochemical yields and high radionuclide purity. The generated injectable [ <superscript>124</superscript> I]NaI solution was sterile, non-pyrogenic and ready for preclinical and clinical applications after a sterile filtration through a 0.22 µm membrane filter.<br /> (Copyright © 2018 Elsevier Ltd. All rights reserved.)

Details

Language :
English
ISSN :
1872-9800
Volume :
140
Database :
MEDLINE
Journal :
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine
Publication Type :
Academic Journal
Accession number :
29936272
Full Text :
https://doi.org/10.1016/j.apradiso.2018.06.014