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dc.contributor.authorAltıkulaç, Aydan
dc.date.accessioned2021-09-23T06:57:35Z
dc.date.available2021-09-23T06:57:35Z
dc.date.issued2021en_US
dc.identifier.issn1018-4619
dc.identifier.issn1610-2304
dc.identifier.urihttps://hdl.handle.net/20.500.12809/9547
dc.description.abstractBuilding materials used in the construction industry, such as marble, granite, ceramics, travertine, and cimstone, are of crustal origin and contain natural radiation. While these materials act as a source of natural radiation inside the building, they actually serve as a shield by blocking external radiation. Therefore, these building materials can also be considered as radiation-shielding materials. In the first part of this study, activity concentrations of radioactive isotopes in materials used in construction industry were determined via gamma spectrometry. The activity concentrations of Ra-226, Th-232 and K-40 radio-active isotopes in marble samples were measured as 10.5, 14.3 and 584.6 Bqkg(-1), respectively. In granite samples, the activity concentrations of radioactive isotopes were found to be 72.3, 63.5, 1024.7 Bqkg(-1), respectively. In ceramic samples, the activity concentrations of radioactive isotopes were found to be 39.8, 68.5, 1338.7 Bqkg(-1), respectively. In the experiment performed using travertine samples, the activity concentrations of radioactive isotopes were calculated to be 5.9, 9.9 and 1338.7 Bqkg(-1), respectively. The activity concentrations of radioactive isotopes in cimstone samples were measured as 6.78, 26.9 and 649.7 Bqkg(-1), respectively. Radium equivalent activity caused by these activities was 21.6, 101.46, 32.29, 91.7, and 47.51 Bqkg(-1) for marble, granite, travertine, ceramic, and cimstone, respectively. The second part of the study focused on the use of building materials as shielding materials. Mass attenuation coefficient mu/rho (cm(2)/gr), and half value layer (HVL) values, representing the radiation interaction with the material used for shielding, were examined individually for nimble, granite, travertine, ceramic, and cimstone samples. The attenuation coefficients were measured for gamma energies from Eu-152, Cs-137, and Co-60 sources. The obtained experimental data were compared with the theoretical values calculated using WinXCom software, and the results were found to be compatible.en_US
dc.item-language.isoengen_US
dc.publisherPARLAR SCIENTIFIC PUBLICATIONSen_US
dc.item-rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectNatural radioactivityen_US
dc.subjectRadiation shieldingen_US
dc.subjectMass attenuation coefficienten_US
dc.subjectBuilding materialen_US
dc.subjectXRFen_US
dc.titleGAMMA RAY RADIATION RESEARCH IN BUILDING MATERIALSen_US
dc.item-typearticleen_US
dc.contributor.departmentMÜ, Ula Ali Koçman Meslek Yüksekokulu, Elektrik Ve Enerji Bölümüen_US
dc.contributor.authorID0000-0001-7270-0530en_US
dc.contributor.institutionauthorAltıkulaç, Aydan
dc.identifier.volume30en_US
dc.identifier.issue9en_US
dc.identifier.startpage10863en_US
dc.identifier.endpage10870en_US
dc.relation.journalFRESENIUS ENVIRONMENTAL BULLETINen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US


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