Attenuation Performance of Heavy Metal-Based Concrete for Neutron Radiation Shielding Materials in Proton Therapy Facilities using Monte Carlo Simulation

Proton therapy is a cancer treatment method that utilizes high-energy protons to deliver radiation doses precisely to tumors by using the Bragg Peak phenomenon. However, the interaction of protons with body tissues can produce secondary neutron radiation, which has the potential to increase the risk of secondary cancers and endanger medical personnel. Therefore, effective shielding materials are needed to reduce neutron radiation exposure. This study aims to evaluate the effectiveness of several shielding materials, including Portland concrete (M0), M1 (zinc oxide and silica nano concrete, 3.02 g/cm³), M2 (concrete with 30% PbO addition, 2.60228 g/cm³), M3 (concrete with Tin and Bismuth alloy addition, 6.238 g/cm³), M4 (Chrome Ore and Titanium Dioxide concrete, 5.1 g/cm³), and M5 (Ferrochrome Slag Aggregate concrete, 2.581 g/cm³), in absorbing proton and neutron radiation. The Monte Carlo simulation method (MCNP) was used to analyze the attenuation parameters, such as linear attenuation coefficient, mass attenuation coefficient and Half Value Layer (HVL). The results showed that M4 material has the best value and attenuation coefficient compared to other materials, making it an optimal choice for shielding with a smaller thickness. Thus, this study provides insight into developing safer and more effective shielding materials for proton therapy facilities.