Radiation Protection Dosimetry Advance Access originally published online on August 11, 2009
Radiation Protection Dosimetry 2009 136(2):101-107; doi:10.1093/rpd/ncp145
| ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
Natural radionuclide content and radiological hazard associated with usage of quartzite sand samples from Ovacik–Silifke–Mersin open pit as building material in Turkey
. Turhan1. Aykam
2lç3,*
1 Turkish Atomic Energy Authority (TAEA), Eskisehir Road 9 km. 06530 Lodumlu, Adana, Turkey
2 General Directorate of Mineral Research and Exploration, Adana, Turkey
3 Mining Engineering Department of Çukurova University, Adana, Turkey
* Corresponding author: amahmutkilic{at}gmail.com
Received January 27, 2009, amended July 3, 2009, accepted July 16, 2009
Activity concentrations of 238U, 232Th, 226Ra and 40K in quartzite sand samples collected from the Ovack–Silifke–Mersin open pit located in the East Mediterranean region of Turkey were determined by using a gamma-ray spectrometry technique. The mean activity concentrations of the 238U, 232Th, 226Ra and 40K in quartzite sand samples were found as 81.7 ± 22.9 Bq kg–1, 6.3 ± 2.8 Bq kg–1, 77.5 ± 24.3 Bq kg–1and 140.0 ± 124.1 Bq kg–1, respectively. The gamma index (I
), the internal exposure index (I
), the indoor absorbed dose rate (Din) and the corresponding annual effective dose (Hin) were evaluated for the public exposure to radiological hazard arising due to the use of quartzite sand samples as building material. The values of I, I, Din and Hin ranged from 0.20 to 0.75, with a mean of 0.34 ± 0.11, 0.23 to 0.77 with a mean of 0.39 ± 0.12, 58.27 to 201.51 nGy h–1 with a mean of 93.33 ± 27.63 nGy h–1 and 0.29 to 0.99 mSv with a mean of 0.46 ± 0.14 mSv, respectively.