Photon shielding response of GNP-reinforced B4C-TiB2 composites: Experimental and MCNP6.2 insights

In this study, the gamma and X-ray radiation attenuation properties of B 4 C-TiB 2 reference ceramics and those reinforced with 1, 2, and 3 vol% graphene nanoplatelets (GNP) were systematically investigated. The composites were fabricated via Spark Plasma Sintering (SPS), enabling rapid densification and controlled microstructural evolution. B 4 C is known for its strong thermal neutron absorption due to its high 10 B content. In addition, it contributes to gamma radiation attenuation through photon absorption and scattering interactions. The incorporation of TiB 2 and GNPs into B 4 C enhances the composite density thereby increasing the photon interaction probability and improving the overall gamma shielding performance. Radiation attenuation measurements of the composites were conducted using 0.356 MeV ( 133 Ba), 0.662 MeV ( 137 Cs), and 1.173 MeV ( 60 Co) sources, and diagnostic X-ray sources (50-110 kVp). Gamma and X-ray attenuation coefficients were independently calculated through MCNP6.2 Monte Carlo simulations to validate the experimental results. The close agreement between simulated and measured values demonstrates the reliability of the computational methodology and its consistency with established theoretical models of photon interaction cross sections. This consistency further supports the applicability of the approach for accurate evaluation and comparative analysis of photon attenuation performance in composite materials. In this study, key photon interaction parameters including the half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Z eff ), and effective electron density (N eff ) were computed. The results indicate that these parameters are significantly dependent on both the photon energy and the chemical composition of the examined composites. Both MCNP and experimental results show that the B 4 C-TiB 2 -GNP composites have linear attenuation coefficients (μ) ranging from 0.1468 to 0.2498 cm −1 , with the sample with 1 vol% GNP (BT1G) exhibits the highest performance, reaching 0.2498 cm −1 for 133 Ba. The results reveal that among all investigated samples, the BT1G composite exhibits the highest shielding efficiency in radiation conditions. GNP-reinforced B 4 C-TiB 2 composites, may serve as a potential alternative to reduce the use of lead in gamma radiation protection.

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Journal
Nuclear Engineering and Technology
Published
2026-08-25
DOI
https://doi.org/10.1016/j.net.2026.104669
Primary Topic
Radiation Shielding Materials Analysis
Type
article
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article

Photon shielding response of GNP-reinforced B4C-TiB2 composites: Experimental and MCNP6.2 insights

Nuri Yorulmaz, Leyla Yanmaz, M. Kamislioglu, İsmail Koçak et al.
Nuclear Engineering and Technology
Radiation Shielding Materials Analysis
article

Photon shielding response of GNP-reinforced B4C-TiB2 composites: Experimental and MCNP6.2 insights

Nuri Yorulmaz, Leyla Yanmaz, M. Kamislioglu, İsmail Koçak, Erhan Ayas, Mehmet Murat Yaşar, Berkay Uygun, Bircan Çalışır, Filiz Çınar Şahin, İskender Atilla Reyhancan, Onur Erbay, B. Büyük, Demet Aydogmus
article en

Abstract

In this study, the gamma and X-ray radiation attenuation properties of B 4 C-TiB 2 reference ceramics and those reinforced with 1, 2, and 3 vol% graphene nanoplatelets (GNP) were systematically investigated. The composites were fabricated via Spark Plasma Sintering (SPS), enabling rapid densification and controlled microstructural evolution. B 4 C is known for its strong thermal neutron absorption due to its high 10 B content. In addition, it contributes to gamma radiation attenuation through photon absorption and scattering interactions. The incorporation of TiB 2 and GNPs into B 4 C enhances the composite density thereby increasing the photon interaction probability and improving the overall gamma shielding performance. Radiation attenuation measurements of the composites were conducted using 0.356 MeV ( 133 Ba), 0.662 MeV ( 137 Cs), and 1.173 MeV ( 60 Co) sources, and diagnostic X-ray sources (50-110 kVp). Gamma and X-ray attenuation coefficients were independently calculated through MCNP6.2 Monte Carlo simulations to validate the experimental results. The close agreement between simulated and measured values demonstrates the reliability of the computational methodology and its consistency with established theoretical models of photon interaction cross sections. This consistency further supports the applicability of the approach for accurate evaluation and comparative analysis of photon attenuation performance in composite materials. In this study, key photon interaction parameters including the half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Z eff ), and effective electron density (N eff ) were computed. The results indicate that these parameters are significantly dependent on both the photon energy and the chemical composition of the examined composites. Both MCNP and experimental results show that the B 4 C-TiB 2 -GNP composites have linear attenuation coefficients (μ) ranging from 0.1468 to 0.2498 cm −1 , with the sample with 1 vol% GNP (BT1G) exhibits the highest performance, reaching 0.2498 cm −1 for 133 Ba. The results reveal that among all investigated samples, the BT1G composite exhibits the highest shielding efficiency in radiation conditions. GNP-reinforced B 4 C-TiB 2 composites, may serve as a potential alternative to reduce the use of lead in gamma radiation protection.

Nuclear Engineering and TechnologyVol. 59(1)
Fırat University (TR), Bandırma Onyedi Eylül University (TR), Eskisehir Technical University (TR), Istanbul Technical University (TR), Harran University (TR)
Sustainable cities and communities
Openalex Percentile: Top 22%
Radiation Shielding Materials Analysis
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