A comparative analysis of shielding effectiveness in glass and concrete containers

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dc.contributor.authorALMmisned, Ghada
dc.contributor.authorSen Baykal, Duygu
dc.contributor.authorElshami, Wiam
dc.contributor.authorSusoy, Gulfem
dc.contributor.authorKilic, Gokhan
dc.contributor.authorTekin, Huseyin Ozan
dc.date.accessioned2024-05-19T14:45:46Z
dc.date.available2024-05-19T14:45:46Z
dc.date.issued2024
dc.departmentİstinye Üniversitesien_US
dc.description.abstractNuclear waste control and related equipment play a vital role in safeguarding human health and the environment from the potential dangers of radioactive waste. This study addresses the critical challenge of enhancing the shielding effectiveness of container materials for nuclear waste management, with a focus on comparing the attenuation properties of glass and concrete composites. Our analysis revealed that the copper oxide-reinforced borosilicate glass container demonstrated a significant transmission factor (TF) value decrease by approximately 15% compared to steel-magnetite concrete at 1.3325 MeV, with a standard deviation of +/- 1.5%, indicating its lower protective characteristics. Nonetheless, it exhibited a 10% higher TF reduction compared to the cement-bitumen mix at the same energy level, with a precision error of +/- 1.2%. In addition, the half-value layer for this glass was determined to be 2.5 cm for 1.3325 MeV gamma rays, showing moderate shielding capacity. The study demonstrates that optimizing the oxide content in the borosilicate glass matrix significantly enhances its shielding effectiveness. This advancement in nuclear waste management materials is justified by our comprehensive evaluation, highlighting the potential of optimized glass materials to outperform traditional concrete in certain scenarios, thus contributing to the development of more effective nuclear waste containment solutions.en_US
dc.description.sponsorshipPrincess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia [PNURSP2024R149]en_US
dc.description.sponsorshipThe authors would like to express their deepest gratitude to Princess Nourah bint Abdulrahman University Researchers Supporting Project number (PNURSP2024R149), Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia.en_US
dc.identifier.doi10.1515/phys-2024-0019
dc.identifier.issn2391-5471
dc.identifier.issue1en_US
dc.identifier.scopus2-s2.0-85191888060en_US
dc.identifier.scopusqualityQ3en_US
dc.identifier.urihttps://doi.org10.1515/phys-2024-0019
dc.identifier.urihttps://hdl.handle.net/20.500.12713/5335
dc.identifier.volume22en_US
dc.identifier.wosWOS:001207932500001en_US
dc.identifier.wosqualityN/Aen_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherDe Gruyter Poland Sp Z O Oen_US
dc.relation.ispartofOpen Physicsen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.snmz20240519_kaen_US
dc.subjectMaterial Propertiesen_US
dc.subjectNuclear Waste Managementen_US
dc.subjectContaineren_US
dc.subjectMonte Carlo Simulationsen_US
dc.titleA comparative analysis of shielding effectiveness in glass and concrete containersen_US
dc.typeArticleen_US

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