Kars İlinde Kullanılan Bazı Yapı Malzemelerindeki Doğal Radyoaktivite ve Radyolojik Tehlikelerin Değerlendirilmesi

Bu çalışmada, Kars ilinde kullanılan bazı yapı malzemelerinin radyoaktivite seviyeleri ve bu malzemelerinin kullanılmasından kaynaklanabilecek radyolojik riskler belirlendi. Kars'ın değişik bölgelerinden 10 farklı yapı malzemesini (kireçtaşı, kil, tras, alçıtaşı, demir cevheri ve dört farklı çimento numunesi) temsil eden toplam 60 numune toplanmıştır. Bu numunelerdeki 226Ra, 232Th ve 40K radyoizotoplarının radyoaktivite konsantrasyonları HPGe gama ışını spektrometre sistemi ile ölçüldü. 226Ra, 232Th ve 40K radyoizotoplarının ortalama radyoaktivite konsantrasyonları sırasıyla 22,87 Bq kg-1, 19,49 Bq kg-1, 265,29 Bq kg-1 ve 1,7 Bq kg-1 olarak bulundu. Elde edilen değerler kullanılarak yapı malzemeleri için radyolojik tehlike indisleri (radyum eşdeğer aktivitesi, yapı içi soğurulmuş doz hızı, yapı içi etkin doz hızı, I? indisi ve I? indisi) hesaplandı. Bu sonuçlar Türkiye'de ve dünyadaki çeşitli ülkelerde benzer malzemeler için bildirilen sonuçlarla kıyaslandı.Bu araştırmanın sonucunda incelenen yapı malzemelerinin radyolojik bir risk oluşturmadığı ve binaların inşasında güvenle kullanılabileceği görülmüştür.

Evaluation of Natural Radioactivity and Radiological Hazards in Some Building Materials Used in Kars

In this study, radioactivity levels of some building materials used in Kars province and radiological risks that could arise from these building materials were determined. A total of 60 samples representing 10 different building materials (limestone, clay, tras, gypsum, iron core and four different cement samples) from various regions of Kars were collected. The radioactivity concentrations of 226Ra, 232Th and 40K radioisotopes in these samples were measured using an HPGe gamma-ray spectrometry system. The mean radioactivity concentrations of 226Ra, 232Th and 40K were found to be 22.87 Bq kg-1, 19.49 Bq kg-1, 265.29 Bq kg-1 and 1.74 Bq kg-1, respectively. Radiation hazard indices (radium equivalent activity, absorbed dose rate indoors, annual effective dose rate indoors, I? index and I? index) were calculated for the building materials using these obtained values. These results were compared with the results reported for similar materials in Turkey and in several countries around the world. As a result of this research, it was observed that the building materials examined did not constitute a radiological risk and could be used safely in the construction of buildings.

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