A critical assessment of the mechanical strength and radiation shielding efficiency of advanced Concrete composites and Vanadium Oxide-Glass container for enhanced nuclear waste management

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dc.authoridHüseyin Ozan Tekin / 0000-0002-0997-3488
dc.authorscopusidHüseyin Ozan Tekin / 56971130700
dc.contributor.authorTekin, Hüseyin Ozan
dc.contributor.authorALMisned, Ghada
dc.contributor.authorKılıç, Gökhan
dc.contributor.authorİlik, Erkan
dc.contributor.authorSusoy, Gülfem
dc.contributor.authorElshami, Wiam E.
dc.contributor.authorIssa, Bashar
dc.date.accessioned2025-04-18T08:20:57Z
dc.date.available2025-04-18T08:20:57Z
dc.date.issued2024
dc.departmentİstinye Üniversitesi, Mühendislik ve Doğa Bilimleri Fakültesi, Bilgisayar Mühendisliği Bölümü
dc.description.abstractThe nuclear industry produces large quantities of low, intermediate, and high levels of radioactive waste, all of which require safe management during both transport and storage. This study evaluates the radiation shielding effectiveness and mechanical properties of four distinct container materials: Pb Composite Glass, 0.5 Cement-0.5 Bitumen, Concrete (Steel-Magnetite), and C9 (BCBV0.5) Vanadium Oxide-Glass. Using Monte Carlo simulations and theoretical methods, we determined the Transmission Factors (TF) and Half-Value Layers (HVL) for each material. The TF indicates the effectiveness of a material in attenuating radiation, calculated by the ratio of gamma rays exiting the material to those entering it. Lower TF values signify better radiation shielding. The HVL is the thickness of material required to reduce the intensity of gamma rays by half, with lower HVL values indicating more effective shielding. Concrete (Steel-Magnetite) demonstrated superior performance with the lowest TF values (e.g., 1.0 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL values (e.g., 2.5 cm at 1.3325 MeV), alongside a high elastic modulus of 163.15 GPa, indicating its robustness for high-energy gamma-ray applications. Pb Composite Glass also showed strong performance with a TF of 9.5 × 10-2 at 0.662 MeV and 1 cm thickness, an HVL of 2.0 cm at 0.662 MeV, and an elastic modulus of 41.54 GPa. The C9 (BCBV0.5) Vanadium Oxide-Glass, with an elastic modulus of 73.79 GPa, outperformed the 0.5 Cement-0.5 Bitumen mixture in both TF (e.g., 1.15 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL (e.g., 4.2 cm at 1.1732 MeV) measurements, highlighting its potential as a more effective alternative. It can be concluded that C9 (BCBV0.5) Vanadium Oxide-Glass presents promising properties for future advancements in radiation protection, warranting further research and optimization. © 2024 The Author(s)
dc.identifier.citationTekin, H. O., ALMisned, G., Kilic, G. Ö. K. H. A. N., Ilik, E. R. K. A. N., Susoy, G., Elshami, W., & Issa, B. (2024). A critical assessment of the mechanical strength and radiation shielding efficiency of advanced Concrete composites and Vanadium Oxide-Glass container for enhanced nuclear waste management. Results in Physics, 64, 107901.
dc.identifier.doi10.1016/j.rinp.2024.107901
dc.identifier.issn22113797
dc.identifier.issnhttp://dx.doi.org/10.1016/j.rinp.2024.107901
dc.identifier.scopus2-s2.0-85200765043
dc.identifier.scopusqualityQ1
dc.identifier.urihttps://hdl.handle.net/20.500.12713/6548
dc.identifier.volume64
dc.indekslendigikaynakScopus
dc.institutionauthorTekin, Hüseyin Ozan
dc.institutionauthoridHüseyin Ozan Tekin / 0000-0002-0997-3488
dc.language.isoen
dc.publisherElsevier B.V.
dc.relation.ispartofResults in Physics
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/openAccess
dc.subjectContainer
dc.subjectMCNP
dc.subjectNuclear Safety
dc.subjectNuclear Waste Management
dc.subjectVanadium Oxide
dc.titleA critical assessment of the mechanical strength and radiation shielding efficiency of advanced Concrete composites and Vanadium Oxide-Glass container for enhanced nuclear waste management
dc.typeArticle

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