Developing new high-temperature shielding materials for neutron radiation protection

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dc.contributor.authorAygun, Bunyamin
dc.contributor.authorKorkut, Turgay
dc.contributor.authorUrtekin, Eren
dc.contributor.authorAlbayrak, Mansur
dc.contributor.authorSayyed, M., I
dc.contributor.authorKarabulut, Abdulhalik
dc.date.accessioned2026-04-25T14:20:09Z
dc.date.available2026-04-25T14:20:09Z
dc.date.issued2026
dc.departmentSinop Üniversitesi
dc.description.abstractIn this paper, neutron shields based on hydraulic lime-based brick samples were fabricated by adding various mass additive materials in proportions such as lime (CaCO3), titanium oxide (TiO2), hematite (Fe2O3), aluminum oxide (Al2O3), calcium sulfate (CaSO4), silicon dioxide (SiO2), and boron carbide (B4C). Neutron attenuation factors such as neutron transmission factor, half-value layer, effective removal cross-section Sigma R (cm-1), mean free path, and neutron flux were determined theoretically using Monte Carlo simulation GEANT4 and Fluka codes. Fast neutron absorption dose rate experiments were performed using a 241Am-Be source and a BF3 gaseous proportional detector. In addition, the absorbed dose values were theoretically determined using the Fluka code. All the obtained data were compared with the results of the examined reference samples (conventional concrete, some heavy concretes, and paraffin). All new brick materials were detected to have superior shielding capacities compared to the reference material. The proposed brick samples can be used as an alternative radiation protection material for regular shielding materials.
dc.identifier.doi10.1093/rpd/ncaf148
dc.identifier.endpage478
dc.identifier.issn0144-8420
dc.identifier.issn1742-3406
dc.identifier.issue5
dc.identifier.orcid0000-0003-2290-9007
dc.identifier.orcid0000-0002-9384-1540
dc.identifier.pmid41420852
dc.identifier.scopus2-s2.0-105035192516
dc.identifier.scopusqualityQ3
dc.identifier.startpage468
dc.identifier.urihttps://doi.org/10.1093/rpd/ncaf148
dc.identifier.urihttps://hdl.handle.net/11486/8408
dc.identifier.volume202
dc.identifier.wosWOS:001642829100001
dc.identifier.wosqualityQ4
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.indekslendigikaynakPubMed
dc.language.isoen
dc.publisherOxford Univ Press
dc.relation.ispartofRadiation Protection Dosimetry
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.snmzKA_WOS_20260420
dc.titleDeveloping new high-temperature shielding materials for neutron radiation protection
dc.typeArticle

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