Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation

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dc.authoridKORKUT, TURGAY/0000-0002-1333-6123
dc.authoridSINGH, VISHWANATH/0000-0001-8659-1961
dc.authoridKarabulut, Abdulhalik/0000-0003-2290-9007
dc.authoridAygun, Bunyamin/0000-0002-9384-1540
dc.contributor.authorAygun, Bunyamin
dc.contributor.authorSakar, Erdem
dc.contributor.authorSingh, V. P.
dc.contributor.authorSayyed, M. I.
dc.contributor.authorKorkut, Turgay
dc.contributor.authorKarabulut, Abdulhalik
dc.date.accessioned2025-03-23T19:38:23Z
dc.date.available2025-03-23T19:38:23Z
dc.date.issued2020
dc.departmentSinop Üniversitesi
dc.description.abstractIn this study, 12 different concentrations of shielding materials were developed and produced. They were covered with high temperature resistant (1500 degrees C) sodium silicate sealing paste. Epoxy resin was produced by adding different percentages of additive materials such as chromium oxide (Cr2O3), lithium (LiF), and nickel oxide (NiO). The GEANT4 and FLUKA codes of the Monte Carlo simulation toolkit were used to determine the mixing ratios. The total macroscopic cross-sections, effective removal cross-sections, mean free path, half value layer, and transmission neutron number were determined for fast neutron radiation using GEANT4 and FLUKA simulation codes. The mass attenuation coefficient, the effective atomic number and half-value layer (HVL) of the samples were calculated using Phy-X/PSD software. The absorbed dose was measured. In this study, an Am-241-Be neutron source with 74 GBq activity and average neutron energy of approximately 4.5 MeV and a BF3 gas detector were used. Both simulation and experimental measurements were compared with paraffin and conventional concrete. The new composite shielding material absorbed radiation much better than the reference materials. This new radiation shielding composite material can be used in nuclear medicine, transport and storage of radioactive waste, nuclear power plants, and as a shielding material for neutron and gamma radiation.
dc.description.sponsorshipProject of Agri Ibrahim Cecen University Scientific Research Projects [MYO 18.001-19.001]
dc.description.sponsorshipThis study was supported by the Project of Agri Ibrahim Cecen University Scientific Research Projects (MYO 18.001-19.001).
dc.identifier.doi10.1016/j.pnucene.2020.103538
dc.identifier.issn0149-1970
dc.identifier.scopus2-s2.0-85095439475
dc.identifier.scopusqualityQ1
dc.identifier.urihttps://doi.org/10.1016/j.pnucene.2020.103538
dc.identifier.urihttps://hdl.handle.net/11486/6140
dc.identifier.volume130
dc.identifier.wosWOS:000598162300003
dc.identifier.wosqualityQ1
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherPergamon-Elsevier Science Ltd
dc.relation.ispartofProgress in Nuclear Energy
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.snmzKA_WOS_20250323
dc.subjectNeutron and gamma radiation
dc.subjectEpoxy
dc.subjectGEANT4
dc.subjectFLUKA
dc.subjectPhy-X/PSD
dc.subjectShielding metal oxide
dc.titleExperimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation
dc.typeArticle

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