TY - JOUR
T1 - Neutron attenuation in GNP-reinforced B4C–TiB2 composites
T2 - Integrated experimental and MCNP6.2 simulation analysis
AU - Kamislioglu, Mirac
AU - Erbay, Onur
AU - Uygun, Berkay
AU - Aydogmus, Demet
AU - Ayas, Erhan
AU - Buyuk, Bulent
AU - Yorulmaz, Nuri
AU - Yasar, M. Murat
AU - Atilla Reyhancan, I.
AU - Cinar Sahin, Filiz
AU - Kocak, Ismail
AU - Calisir, Bircan
N1 - Publisher Copyright:
© 2025 Elsevier Ltd
PY - 2026/2
Y1 - 2026/2
N2 - 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 (ΣTot) values determined for the GNP-reinforced B4C–TiB2 composites were investigated. Among them, the sample containing 1 vol% GNP exhibited a slightly higher ΣTot 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.
AB - 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 (ΣTot) values determined for the GNP-reinforced B4C–TiB2 composites were investigated. Among them, the sample containing 1 vol% GNP exhibited a slightly higher ΣTot 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.
KW - Detection system
KW - GNP-Reinforced BC–TiB composites
KW - Neutron howitzer (Pu–Be) source
KW - Neutron radiation
KW - Thermal neutrons
UR - https://www.scopus.com/pages/publications/105016455492
U2 - 10.1016/j.radphyschem.2025.113326
DO - 10.1016/j.radphyschem.2025.113326
M3 - Article
AN - SCOPUS:105016455492
SN - 0969-806X
VL - 239
JO - Radiation Physics and Chemistry
JF - Radiation Physics and Chemistry
M1 - 113326
ER -