Chattopadhyay Sankha, Das Sujata Saha, Barua Luna
Radiopharmaceuticals 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.
Appl Radiat Isot. 2010 Jan;68(1):1-4. doi: 10.1016/j.apradiso.2009.07.024. Epub 2009 Aug 14.
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.
描述了一种简单且廉价的从通过(98)Mo经(98)Mo(n,γ)(99)Mo核反应中子活化产生的(99)Mo中分离(99m)Tc的方法。(99m)Tc的回收通过溶剂萃取技术,随后进行柱(活性氧化铝)色谱法。完全分离(99m)Tc的总放射化学产率为85 - 95%(n = 10)。分离出的Na[(99m)Tc]TcO₄具有高放射性核纯度、放射化学纯度和化学纯度。该方法可用于医院放射性药房常规使用利用研究反应堆产生的低 - 中比活度(n,γ)(99)Mo的(