Accurate Monte Carlo modeling of cyclotrons for optimization of shielding and activation calculations in the biomedical field. (November 2015)

• Record Type: Journal Article
• Authors: Infantino, Angelo; Marengo, Mario; Baschetti, Serafina; Cicoria, Gianfranco; Longo Vaschetto, Vittorio; Lucconi, Giulia; Massucci, Piera; Vichi, Sara; Zagni, Federico; Mostacci, Domiziano
• Is Part Of: Radiation physics and chemistry. Volume 116(2015:Nov.)
• Page Start: 231
• Page End: 236
• Publication Date: 2015-11
• Subjects: Cyclotron -- Monte Carlo -- FLUKA -- PET -- Shielding -- Optimization; Radiation chemistry -- Periodicals; Radiometry -- Periodicals; Radiation -- Periodicals; Chimie sous rayonnement -- Périodiques; 539.2
• DOI: 10.1016/j.radphyschem.2015.01.001
• Languages: English
• ISSNs: 0969-806X

Abstract

Abstract: Biomedical cyclotrons for production of Positron Emission Tomography (PET) radionuclides and radiotherapy with hadrons or ions are widely diffused and established in hospitals as well as in industrial facilities and research sites. Guidelines for site planning and installation, as well as for radiation protection assessment, are given in a number of international documents; however, these well-established guides typically offer analytic methods of calculation of both shielding and materials activation, in approximate or idealized geometry set up. The availability of Monte Carlo codes with accurate and up-to-date libraries for transport and interactions of neutrons and charged particles at energies below 250 MeV, together with the continuously increasing power of nowadays computers, makes systematic use of simulations with realistic geometries possible, yielding equipment and site specific evaluation of the source terms, shielding requirements and all quantities relevant to radiation protection. In this work, the well-known Monte Carlo code FLUKA was used to simulate two representative models of cyclotron for PET radionuclides production, including their targetry; and one type of proton therapy cyclotron including the energy selection system. Simulations yield estimates of various quantities of radiological interest, including the effective dose distribution around the equipment, the effective number of neutron produced per incident proton and the activation of target materials, the structure of the cyclotron, the energy degrader, the vault walls and the soil. The model was validated against experimental measurements and comparison with well-established reference data. Neutron ambient dose equivalent H ⁎ (10) was measured around a GE PETtrace cyclotron: an average ratio between experimental measurement and simulations of 0.99±0.07 was found. Saturation yield of 18 F, produced by the well-known 18 O(p, n) 18 F reaction, was calculated and compared with the IAEA recommended value: a ratio simulation to IAEA of 1.01±0.10 was found. Highlights: Monte Carlo model of different biomedical cyclotron facilities were developed. Models were validated experimentally for some quantities of radiological interest. Good agreement with experimental measurements and theoretical data was achieved. Validated MC models establish a tool for planning new cyclotron facilities. Examples and practical cases are reported.