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Updated: Jun 20, 2026
Preparation and Evaluation of 99mTc-labeled Tridentate Chelates for Pre-targeting Using Bioorthogonal Chemistry
Published on: February 4, 2017
A simple and rapid technique for recovery of (99m)Tc from low specific activity (n,gamma)(99)Mo based on solvent
Sankha Chattopadhyay1, Sujata Saha Das, Luna Barua
1Radiopharmaceuticals Laboratory, Regional Centre, Board of Radiation and Isotope Technology (BRIT), Variable Energy Cyclotron Centre (VECC), 1/AF, Bidhan Nagar, Kolkata, West Bengal 700 064, India. sankha@veccal.ernet.in
Abstract:
A simple and inexpensive method of separation of (99m)Tc from (99)Mo produced by neutron activation of (98)Mo via the (98)Mo(n,gamma)(99)Mo nuclear reaction is described. The recovery of (99m)Tc was performed by solvent extraction technique followed by column (active alumina) chromatography. The overall radiochemical yield for the complete separation of (99m)Tc was 85-95% (n=10). The separated Na[(99m)Tc]TcO(4) was of high radionuclidic, radiochemical, and chemical purities. The method can be adopted for routine use of (99m)Tc in hospital radio-pharmacies utilizing low-medium specific activity (n,gamma)(99)Mo produced in a research reactor.
