Usage of the FLUKA simulation code to determining shield materials for proton accelerators

Radiation fields with high-intensity and high-energy are formed as a result of the interactions of protons with the target or the accelerator components in low-energy proton accelerators. Shielding is made for being under permissible dose limit of these radiation fields that effect on radiation workers and public.A tunnel which dimensions of 6mx5mx10m was defined for shielding of 50-250 MeV protons. In the tunnel, a roof 4m and side walls 3m away from the beam axis. Standard concrete and soil samples in different density were collected as the shielding material for determining the minimum shield thicknesses of the side walls and roof. The thicknesses of side walls and roof are taken as maximum for estimating required values of shield thicknesses.Thicknesses of standard concrete and soil shield were determined according to non-designated, supervised and controlled areas from equivalent dose distributions that estimated for different proton energies. In addition the thickness variations are investigated by adding different amount of B4C to standard concrete. When standard concrete is selected as shielding material, dose distributions for protons in the energy range of 50-250 MeV were examined. The side walls of the tunnel are arranged according to non-designated area dose limits, in case the roof is arranged according to controlled areas.The purpose of this study is to determine tunnel design, shielding thicknesses and distribution of equivalent dose for proton accelerator that planning to build within Turkish Accelerator Center.