Decommissioning Procedures For An 11 Mev Self-Shielded Medical Cyclotron After 16 Years Of Working Time

The present article describes the decommissioning of a compact, self-shielded, 11 MeV medical cyclotron. A Monte Carlo simulation of the possible nuclear reactions was performed in order to plan the decommissioning activities. In the course of the cyclotron dismantling, cyclotron components, shields, and floor concrete samples were measured. Residual activities were analyzed with a Ge(Li) detector and compared with simulation data. Doses to staff involved in the decommissioning procedure were monitored by individual TL dosimeters. The simulations identified five radioactive nuclides in shields and floor concrete: Fe-55 and Ca-45 (beta emitters, total specific activity: 2.29 x 10(4) Bq kg(-1)) and Eu-152, (EU)-E-154, Co-60 (gamma emitters, total specific activity: 1.62 x 10(3) Bq kg(-1)). Gamma-ray spectrometry confirmed the presence of gamma emitters, corresponding to a total specific activity of 3.40 x 10(2) Bq kg(-1). The presence of the radioisotope Sb-124 in the lead contained in the shield structure, corresponding to a simulated specific activity of 9.38 X 10(3) Bq kg(-1), was experimentally confirmed. The measured dose from external exposure of the involved staff was < 20 mu Sv, in accordance with the expected range of values between 10 and 20 mu Sv. The measured dose from intake was negligible. Finally, the decommissioning of the 11 MeV cyclotron does not represent a risk for the involved staff, but due to the presence of long-lived radioisotopes, the cyclotron components are to be treated as low level radioactive waste and stored in an authorized storage area.