Feasibility studies for production of 89Sr in the Fast Breeder Test Reactor (FBTR)

Abstract

Summary 89Sr, a pure beta emitter with half life of 50.53 d is used as its chloride solution for palliative care of bone metastases. This paper describes the feasibility studies that have been conducted at FBTR, IGCAR for production of this radionuclide using the 89Y(n, p)89Sr reaction. Yttria pellets were irradiated in a special subassembly at the core centre for a total of 73 d in two steps of 35 d and 38 d with a time gap of 38 d. The irradiated yttria target was dissolved in nitric acid and the bulk Y was separated by solvent extraction using the TBP-HNO3 complex. The 89Sr fraction was purified using the cation exchange resin DOWEX 50W×8 (100-200 mesh size) from the other radioactive impurities seen. The eluted 89Sr fraction was assayed using a GM counting system. The 89Sr activity produced in 1 g of yttria pellet was found to be 19 mCi.