Radiation attenuation analysis of different layered material configurations with a 241Am-Be source using PHITS

Abstract

Neutron radiation poses significant challenges in shielding design due to its high penetration capability and ability to induce secondary radiation through nuclear interactions. This study investigates radiation attenuation across different layered material configurations exposed to a ²⁴¹Am-Be source. Neutron and gamma dose distributions were computed using the PHITS Monte Carlo simulation code, while interpolation was employed to evaluate the influence of material thickness on dose attenuation. Results indicate that both neutron and gamma doses are strongly governed by the materials' neutron cross sections, the extent of secondary gamma production, and the arrangement and thickness of shielding layers. Among the configurations examined, the Tungsten-BPE-Concrete combination exhibited the most effective attenuation performance. These findings provide valuable insights into neutron-matter interactions and offer practical guidance for optimizing multilayer shielding systems in radiation protection applications.