Neutron attenuation in GNP-reinforced B₄C–TiB₂ composites: Integrated experimental and MCNP6.2 simulation analysis

This study investigates the neutron radiation attenuation properties of B₄C–TiB₂ reference composites and B₄C–TiB₂-GNP composites reinforced with 1, 2, and 3 vol% graphene nanoplatelets (GNP), fabricated via Spark Plasma Sintering (SPS). B₄C offers excellent neutron shielding owing to its unique absorption property, while TiB₂ and GNP additions to B₄C can further enhance its shielding capability due to their combined density enhancement effects. Neutron transmission tests were carried out using a Nuclear-Chicago Howitzer-3 (NH-3) equipped with a 5-Ci ²³⁹Pu–Be neutron source. The total macroscopic cross-section (Σ_Tot) values determined for the GNP-reinforced B₄C–TiB₂ composites were investigated. Among them, the sample containing 1 vol% GNP exhibited a slightly higher Σ_Tot value compared to the other compositions. Thermal neutron attenuation was also evaluated through MCNP6 Monte Carlo simulations to validate experimental data. A strong correlation between simulated and measured results confirms the accuracy and consistency of the adopted methodology, and the results align with established literature. The findings demonstrate the promising potential of GNP-reinforced B₄C–TiB₂ composites as multifunctional materials for advanced nuclear radiation shielding applications, particularly in the energy sector, as well as in the aerospace and defense sectors.