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Recovery of 131I from alkaline solution of n-irradiated tellurium target using a tiny Dowex-1 column
Sankha Chattopadhyay1, Sujata Saha Das
1Radiopharmaceuticals Laboratory, Regional Centre, Board of Radiation and Isotope Technology, Variable Energy Cyclotron Centre (VECC), 1/AF, Bidhan Nagar, Kolkata- 700 064, India. sankha@veccal.ernet.in
Abstract:
A simple and inexpensive ion-exchange chromatography method for the separation of medically useful no-carrier-added (nca) iodine radionuclides from bulk amounts of irradiated tellurium dioxide (TeO(2)) target was developed and tested using (131)I. The radiochemical separation was performed using a very small Dowex-1x8 ion-exchange column. The overall radiochemical yield for the complete separation of (131)I was 92+/-1.8 (standard deviation) % (n=8). The separated nca (131)I was of high, approximately 99%, radionuclidic and radiochemical purity and did not contain detectable amounts of the target material. This method may be adopted for the radiochemical separation of other different iodine radionuclides produced from tellurium matrices through cyclotron as well as reactor irradiation.
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