Development of ~(90)Sr-~(90)Y Generator Systems for Radio Therapeutic Applications

摘要

~(90)Y in carrier-free form is a potential therapeutic radioisotope due to its several desirable nuclear properties. It is a pure beta emitter with 64. ih half life and 2.28 MeV energy formed by the decay of ~(90)Sr. ~(90)Sr is available in good yield during the fission of heavy nuclides and can be recovered in large quantities from high level liquid waste originating from PUREX process used in spent fuel reprocessing and is an ideal source for generator applications due to its long half life. A number of generator systems based on solvent extraction, ion exchange, extraction chromatography, electrochemical etc. are reported in literature, but none of them satisfy the requirement of an ideal system for use in radiopharmaceutical centers. Purity of the product and ease in handling of the system are the two major requirements. This has prompted to develop a generator system for routine application. Feed ~(90)Sr and solvents used in these studies are of indigenous origin. The techniques used have been progressively changed from extraction chromatography through single membrane cell to the current two membrane cell configuration. The present paper describes the step by step evolution of the generator system based on supported liquid membrane technique to its current status. The system is currently configured at an ideal level of 100 mCi for routine use and can be multiplied with additional units as per demand. During the course of generator development, a simple and novel quality control technique based on extraction paper chromatography was also perfected for the first time.