An investigation of neutron shielding and activation performances of four types of concrete for carbon ion therapy facility

Abstract

Carbon ions have unique physical and biological properties that allow for precise targeting of tumors while minimizing damage to surrounding healthy tissues. The emitted neutrons dominate the radiation field in the treatment room and pose challenges for radiological shielding. Concrete is extensively utilized in the construction of radiotherapy facilities due to its good shielding characteristics, and it can be easily poured into the desired shapes and thickness. The difference in composition of concrete affects the characteristics of neutron attenuation and activation performance. Therefore, the purpose of this study is to clarify the shielding properties and activation performances of four types of concrete for carbon ion therapy facilities. The Monte Carlo method is used to analyze the neutron spectra from thick targets upon carbon ion bombardment. Furthermore, the deep attenuation efficiency of the secondary neutron in different compositions of concrete is discussed. The shielding design is developed to ensure compliance with the prescribed dose limit outside the shielding during operation. Finally, the induced radioactivity in concrete is estimated for both short-term and long-term operation. The produced radionuclides inventories and depth profiling are determined. This study reveals the shielding and radioactivity issue of carbon ion therapy facilities and is expected to aid in the design or construction of similar facilities.