Development of the Purification Process of Gallium-68 Eluted from Germanium-68/Gallium-68 Generator

dc.contributor.authorSriprapa T.
dc.contributor.authorDoungta T.
dc.contributor.authorSritongkul N.
dc.contributor.authorTantawiroon M.
dc.contributor.correspondenceSriprapa T.
dc.contributor.otherMahidol University
dc.date.accessioned2024-03-06T18:06:14Z
dc.date.available2024-03-06T18:06:14Z
dc.date.issued2024-01-01
dc.description.abstractObjective: 68Ga has a half-life of 68 minutes, with 89% of its decay is through positron emission. It is available from generator systems and possesses suitable property for labeling radioligands. These aspects make 68Ga a promising tracer for positron emission tomography (PET) imaging. This study aims to develop the purification process of the 68Ga eluates from 68Ge/68Ga generator after its recommended shelf-life and ensuring the quality through the radiolabeling process. Materials and Methods: In this study, we explored the development of a purification method for 68Ga eluted from a 68Ge/68Ga generator before radiolabeling was investigated. Cation and anion exchange chromatography techniques were combined to remove trace amounts of competing metal ion impurities. Post-purification, the eluate’s metal contents were analyzed using inductively coupled plasma atomic emission spectroscopy (ICP-AES). Breakthrough of 68Ge was measured using a multi-channel analyzer (MCA) spectrometer with high-purity germanium (HPGe) radiation detectors. Additionally, the radiochemical purity of 68Ga-NOTA-RGD was analyzed by high-performance liquid chromatography (HPLC). Results: Metal impurities including Fe(II), Zn(II) and Al(III) were reduced by 61%, 38% and 44% respectively. The 68Ge breakthrough was approximately ~10-3%. The labeling efficiency with NOTA-RGD, a tracer for angiogenesis imaging, resulted in an average yield of 68Ga-NOTA-RGD (not corrected for decay) of around 50%, with a radiochemical purity by HPLC of approximately 98%-99%. Conclusion: Cation exchange in combination with anion exchange chromatography was thus proven to be an efficient method for purification of the 68Ga eluate from a 68Ge/68Ga generator prior to labeling the 68Ga PET radiotracer.
dc.identifier.citationSiriraj Medical Journal Vol.76 No.2 (2024) , 90-96
dc.identifier.doi10.33192/smj.v76i2.266113
dc.identifier.eissn22288082
dc.identifier.scopus2-s2.0-85185946222
dc.identifier.urihttps://repository.li.mahidol.ac.th/handle/20.500.14594/97466
dc.rights.holderSCOPUS
dc.subjectMedicine
dc.titleDevelopment of the Purification Process of Gallium-68 Eluted from Germanium-68/Gallium-68 Generator
dc.typeArticle
mu.datasource.scopushttps://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=85185946222&origin=inward
oaire.citation.endPage96
oaire.citation.issue2
oaire.citation.startPage90
oaire.citation.titleSiriraj Medical Journal
oaire.citation.volume76
oairecerif.author.affiliationSiriraj Hospital
oairecerif.author.affiliationThailand Institute of Nuclear Technology

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