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Recovery of 131I from alkaline solution of n-irradiated tellurium target using a tiny Dowex-1 column.

Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine (2010-05-18)
Sankha Chattopadhyay, Sujata Saha Das
RESUMEN

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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Sigma-Aldrich
Tellurium dioxide, ≥99%
Sigma-Aldrich
Tellurium dioxide, 99.995% trace metals basis
Sigma-Aldrich
Tellurium dioxide, ≥97.0%