Production cross-section and reaction yield of 82Sr for 82Sr/82Rb generator

Abstract

There are many radioisotopes used for diagnostic and therapeutic purposes in nuclear medicine. One of the radioisotopes used for diagnostic purposes is 82Rb. It is used in positron emission tomography (PET) as to be positron emitter and commonly obtained from 82Sr/82Rb generator. In this study, we have investigated some possible production mechanisms of 82Sr by regarding 82Sr/82Rb generator. 85,87Rb(p,xn)82Sr and 80,82,83,84,86Kr(3He,xn)82Sr reaction channels have been investigated using the CTFGM, BSFGM, and GSM models within the framework of TALYS nuclear reaction code. It has been seen that the production cross-sections, reaction yields and total activation values calculated up to 60 MeV beam energy value are in agreement with the available data in the literature.