Development of phenolic resin-based composite materials and investigation of their radiation protection characteristics

This study covers the development of phenolic resin-based composite materials with the ability to shield gamma and fast neutron radiation, as well as the investigation of their radiation protection characteristics. The design and production of new phenolic resin-based composite materials were carried out using various materials such as polyurethane (PU), lithium fluoride (LiF), glass fiber (GF), nickel oxide (NiO), iron oxide (Fe2O3), titanium oxide (TiO), lithium borate (Li2B4O7), chromium oxide (Cr2O3), aramid fiber, tungsten trioxide (WO3), and zirconium (ZrO). Gamma-ray mass attenuation coefficient, linear attenuation coefficient, mean free path, and half-value layer were calculated using the WinXCom program. Shielding parameters for fast neutrons, such as total macroscopic cross-section, mean free path, half-value layer, and the number of transmitted neutrons, were calculated theoretically using the GEANT4 code program. In addition, experimental equivalent dose measurements were carried out using a 241Am-Be fast neutron source, and the neutron radiation absorption capacities of the samples were determined. The obtained results were compared with P: Paraffin, OC: Ordinary concrete, H-SC: Hematite-serpentinite concrete, I-LC: Ilmenite-limonite concrete, B-MC: Basalt-magnetite concrete, and IC: Ilmenite concrete, showing that the new metal oxide composite materials could effectively absorb fast neutron radiation. It is suggested that these new types of metal oxide composite materials could be used for shielding purposes in nuclear applications.