High efficiency production and purification of 86Y based on electrochemical separation.

As an intermediate half-life positron emitter (86)Y is an attractive radioisotope for positron emission tomography (PET) studies, particularly for patient specific dosimetry planning of (90)Y-based radiotherapy procedures. It can be conveniently produced by a small-sized cyclotron via the (86)Sr(p,n)(86)Y nuclear reaction. The optimization of the electrochemical separation of (86)Y from the target material and its purification was done by modeling the whole production cycle using (90)Y.