Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron
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Sankha Chattopadhyay
,
Samarjit Singha
Abstract
Gallium-68 [t1/2: 67.7 min, β+ (89 %)] has application in PET imaging mainly for prostate cancer and neuroendocrine tumours. Gallium-68 is generally obtained from a 68Ge/68Ga generator. It is therefore an important task to prepare 68Ge (t1/2 = 271 days) radiochemical for the manufacture of 68Ge/68Ga generator to cater for the needs of various nuclear medicine centres. Germanium-68 has been produced successfully after irradiation of indigenously developed Ga–Ni targets in a 30 MeV cyclotron and chemical processing of the irradiated targets using an indigenous semi-automated module. The Ga–Ni targets were prepared by an electroplating method. The 68Ge has been radiochemically separated from irradiated Ga–Ni targets using Sephadex G-25 column chromatography. The chemical separation yield and radionuclidic purity of 68Ge were about 70 % (n = 3) and about 98.3 % (n = 3), respectively.
Acknowledgments
The authors acknowledge Pradip Mukherjee, Chief Executive, Board of Radiation and Isotope Technology and Dr. Sumit Som, Director, Variable Energy Cyclotron Centre for their support in the work and the cyclotron personnel in Medical Cyclotron Facility, VECC for their contribution in smooth cyclotron operation. Arpit Mitra is acknowledged for providing gold plated copper base material for target preparation.
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Research ethics: The authors declare that they have no known conflict in research ethics.
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Author contributions: Sankha Chattopadhyay: Writing – original draft, Supervision, Project administration, Methodology, Investigation. Samarjit Singha: Methodology, Investigation. Shayantani Ash: Methodology, Investigation. Luna Barua: Methodology. D.G. Mahesh: Methodology Sujata Saha Das: Methodology. Madhusmita: Methodology. Md Alam Nayer: Methodology. Umesh Kumar: Methodology. Suprakash Roy: Cyclotron operation supervision. Prosenjit Dhang: Cyclotron operation. Santu Dey: Characterization of target.
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Competing interests: The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
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Research funding: This research did not receive any specific grant from funding agencies in the public, commercial, or not-for-profit sectors.
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Data availability: No data was used for the research described in the article.
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Articles in the same Issue
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Articles in the same Issue
- Frontmatter
- Preface
- NUCAR-2023: Foreword
- Research Articles
- Theoretical analysis of light and heavy-ion induced reactions: production of medically relevant 97Ru
- Excitation functions of alpha-particle induced nuclear reactions on nat Sn
- Non-destructive assay of plutonium in absence of gamma-ray spectrometry
- Catalytic destruction of oxalate in the supernatant stream generated during plutonium reconversion process
- Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy
- Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells
- Zirconium sponge production: an integrated approach for chemical characterization of process intermediates using ICP-OES
- Determination of 10B/11B in boric acid and B4C using LA-ICPMS
- Evaluating sustainability of Bhuj aquifer system, Western India using nuclear dating techniques
- Nanocrystalline Ce(OH)4-based materials: ruthenium selective adsorbent for highly alkaline radioactive liquid waste
- Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron
- Preparation of [64Cu]Cu–NOTA complex as a potential renal PET imaging agent using 64Cu produced via the direct activation route
- Total chemical synthesis of PSMA-617: an API for prostate cancer endotherapeutic applications
- Rapid screening technique for gross α and gross β estimations in aqueous samples during radiation emergency
- Development of Dy3+ doped lithium magnesium borate glass system for thermoluminescence based neutron dosimetry applications
