Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron
Author:
Chattopadhyay Sankha1, Singha Samarjit1, Ash Shayantani1, Barua Luna1, Mahesh Devaraj G.1, SahaDas Sujata1, Madhusmita 1, Alam Md. Nayer1, Kumar Umesh1, Roy Suprakash2, Dhang Prosenjit2, Dey Santu3
Affiliation:
1. Regional Centre, Board of Radiation and Isotope Technology, Medical Cyclotron Facility , Variable Energy Cyclotron Centre , 1/AF, Bidhan Nagar , Chakgaria , Kolkata 700 064 , India 2. Medical Cyclotron Facility , Variable Energy Cyclotron Centre , Chakgaria , Kolkata , India 3. Variable Energy Cyclotron Centre , Salt Lake , Kolkata , India
Abstract
Abstract
Gallium-68 [t
1/2: 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 (t
1/2 = 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.
Publisher
Walter de Gruyter GmbH
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