Bursa’da Kullanılan Yapı Malzemelerinde Doğal Radyonüklit Analizi

Year 2025, Volume: 30 Issue: 2, 524 - 536, 31.08.2025

Mağrur Baş , Abdullah Mavi , Nergiz Yıldız Yorgun

https://doi.org/10.53433/yyufbed.1674395

Abstract

Bu makalede, Bursa ilinde yapı malzemesi olarak kullanılan çimento, tuğla, kum ve alçı ile yüzey malzemelerinden mermer, fayans ve derz dolgu örnekleri (27 adet) rastgele toplandı. Örneklerin 226Ra, 232Th ve 40K radyonüklit aktivite konsantrasyonları NaI(Tl) gama ışını spektrometresi ile ölçüldü. Sonuçlar analiz edildiğinde, 226Ra, 232Th ve 40K aktivite konsantrasyonlarının sırasıyla BDL - 81.16 Bq kg-1, BDL - 94.22 Bq kg-1, BDL – 781.26 Bq kg-1 arasında değiştiği gözlendi. 226Ra ve 232Th aktivitesinin en yüksek ortalama değerleri sırasıyla 33.6 ve 43.2 Bq kg−1 ile çimento örneklerine ait iken 40K için ölçülen en yüksek ortalama değer 771.2 Bq kg−1 ile tuğla örneklerine aittir. Ayrıca numunelerdeki radyolojik tehlikeleri değerlendirmek için, elde edilen aktivite değerleri kullanılarak radyum eşdeğer aktivitesi (Raeq), iç hava emilen doz hızı (Din), yıllık etkin doz hızı (AEDEin), dış tehlike indeksi (Hex), iç tehlike indeksi (Hin) ve gama indeksi hesaplandı (Ig). Raeq değerleri, uluslararası olarak kabul edilen 370 Bq kg-1 sınır değerinin altındadır. Çimento 2, Çimento 4 ve Çimento 7 numuneleri dışında tüm yapı malzemeleri için Din değerleri kabul edilebilir limit değer aralığındadır. Bu yapı malzemeleri için, AEDEin, Hex, Hin ve Ig değerleri önerilen birim sınırın altındadır ve radyolojik risk oluşturmazlar. Bu özellikleri ile söz konusu malzemeler inşaat malzemesi olarak önerilebilir.

Keywords

Gama aktivite konsantrasyon indisi , Na(I)Tl dedektörü , Radyum eşdeğer aktivitesi , Yapı malzemeleri

Natural Radionuclide Analysis in Building Materials Used in Bursa

Abstract

In this study, a total of 27 samples of cement, brick, sand and plaster used as construction materials and marble, tile and grout from surface materials in Bursa province were randomly collected. 226Ra, 232Th and 40K radionuclide activity concentrations of the samples were measured by NaI(Tl) gamma-ray spectrometer. When the results were analyzed, it was observed that 226Ra, 232Th and 40K activity concentrations varied between BDL (Below Detection Limit) - 81.16 Bq kg-1, BDL - 94.22 Bq kg-1, BDL - 781.26 Bq kg-1, respectively. The highest mean values of 226Ra and 232Th activities belong to the cement samples with 33.6 and 43.2 Bq kg−1, respectively, while the highest average value measured for 40K belongs to the brick samples with 771.2 Bq kg−1. In addition, to evaluate the radiological hazards in the samples, radium equivalent activity (Raeq), indoor air absorbed dose rate (Din), annual effective dose rate (AEDEin), external hazard index (Hex), internal hazard index (Hin), and gamma index (Ig) were calculated using the obtained activity values. Raeq values are below the internationally accepted limit value of 370 Bq kg-1. Din values for all construction materials except Cement 2, Cement 4 and Cement 7 samples are within the acceptable limit value range. For these building materials, the AEDEin, Hin, Hex and Ig values are below the recommended unit limit and do not pose radiological risk. With these properties, these materials can be recommended as construction materials.

Keywords

Building materials , Gamma activity concentration index , NaI(Tl) detector , Radium equivalent activity

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