Development of the Purification Process of Gallium-68 Eluted from Germanium-68/Gallium-68 Generator
dc.contributor.author | Sriprapa T. | |
dc.contributor.author | Doungta T. | |
dc.contributor.author | Sritongkul N. | |
dc.contributor.author | Tantawiroon M. | |
dc.contributor.correspondence | Sriprapa T. | |
dc.contributor.other | Mahidol University | |
dc.date.accessioned | 2024-03-06T18:06:14Z | |
dc.date.available | 2024-03-06T18:06:14Z | |
dc.date.issued | 2024-01-01 | |
dc.description.abstract | Objective: 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.citation | Siriraj Medical Journal Vol.76 No.2 (2024) , 90-96 | |
dc.identifier.doi | 10.33192/smj.v76i2.266113 | |
dc.identifier.eissn | 22288082 | |
dc.identifier.scopus | 2-s2.0-85185946222 | |
dc.identifier.uri | https://repository.li.mahidol.ac.th/handle/20.500.14594/97466 | |
dc.rights.holder | SCOPUS | |
dc.subject | Medicine | |
dc.title | Development of the Purification Process of Gallium-68 Eluted from Germanium-68/Gallium-68 Generator | |
dc.type | Article | |
mu.datasource.scopus | https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=85185946222&origin=inward | |
oaire.citation.endPage | 96 | |
oaire.citation.issue | 2 | |
oaire.citation.startPage | 90 | |
oaire.citation.title | Siriraj Medical Journal | |
oaire.citation.volume | 76 | |
oairecerif.author.affiliation | Siriraj Hospital | |
oairecerif.author.affiliation | Thailand Institute of Nuclear Technology |