Browsing by Author "Gezer, F."

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Evaluation of potential exposure risks of natural radioactivity levels emitted from building materials used in Adana, Turkey
(Indoor and Built Environment 2014 23: 594 originally published online 29 May 2012, 2012-05-29) Turhan, Şeref; Solak, S.; Uğur, F.A.; Gören, E.; Gezer, F.; Yeğingil, Z.; Yeğingil, İ.
In this paper, the natural radioactivity levels in a total of 117 samples of 14 different building materials collected from building construction sites and from the retailers in Adana were studied by means of gamma-ray spectrometer with HPGe detector. The mean activity concentrations of 226Ra, 232Th and 40K measured in the studied building material samples ranged from 2.1 to 88.2 Bq kg1 , 1.8 to 52.7 Bq kg1 and 68.1 to 847.5 Bq kg1 for 226Ra, 232Th and 40K radionuclide, respectively. The external and internal index, the indoor absorbed dose rate and the corresponding annual effective dose were evaluated for potential exposure risks from the usage of the building material samples. The evaluated values of the external and internal index were below the recommended upper level. All the values of effective annual dose determined were lower than recommended exemption level of 0.3 mSv. The results suggest that the use of the studied building material samples in the construction of buildings is unlikely to give rise to any significant radiation exposure to the residents.
Evaluation of potential exposure risks of natural radioactivity levels emitted from building materials used in Adana, Turkey
(Indoor and Built Environment 2014 23: 594 originally published online 29 May 2012, 2012) Turhan, Şeref; Solak, S.; Uğur, F.A.; Gören, E.; Gezer, F.; Yeğingil, Z.; Yeğingil, İ.
In this paper, the natural radioactivity levels in a total of 117 samples of 14 different building materials collected from building construction sites and from the retailers in Adana were studied by means of gamma-ray spectrometer with HPGe detector. The mean activity concentrations of 226Ra, 232Th and 40K measured in the studied building material samples ranged from 2.1 to 88.2 Bq kg 1, 1.8 to 52.7 Bq kg 1 and 68.1 to 847.5 Bq kg 1 for 226Ra, 232Th and 40K radionuclide, respectively. The external and internal index, the indoor absorbed dose rate and the corresponding annual effective dose were evaluated for potential exposure risks from the usage of the building material samples. The evaluated values of the external and internal index were below the recommended upper level. All the values of effective annual dose determined were lower than recommended exemption level of 0.3 mSv. The results suggest that the use of the studied building material samples in the construction of buildings is unlikely to give rise to any significant radiation exposure to the residents.
INVESTIGATION OF THE ACTIVITY LEVEL AND RADIOLOGICAL IMPACTS OF NATURALLY OCCURRING RADIONUCLIDES IN BLAST FURNACE SLAG
(Radiation Protection Dosimetry (2012), pp. 1–7, 2012) Turhan, Şeref; Uğur, F.A.; Şahan, H.; Gören, E.; Gezer, F.; Yeğingil, Z.
The activity level and possible radiological impacts of naturally occurring radionuclides on the health of workers and members of the public, as a result of utilisation of blast furnace slag (BFS) samples as a substitute for aggregate in road construction were investigated by using a gamma-ray spectrometer and potential exposure scenarios given in Radiation Protection 122. The mean activity concentrations of the 226Ra, 232Th and 40K in BFS samples were found to be 152.4, 54.9 and 183.1 Bq kg21, respectively. These values are compared with typical values measured in BFS samples from the European Union countries, which are 270, 70 and 240 Bq kg21 for 226Ra, 232Th and 40K, respectively. The values of radium equivalent activity index calculated for BFS samples were within the recommended safety limits. The highest total annual effective doses evaluated as 0.9 and 0.4 mSv y21 for members of the public and workers, respectively, were lower than the annual limit of 1 mSv y21.
INVESTIGATION OF THE ACTIVITY LEVEL AND RADIOLOGICAL IMPACTS OF NATURALLY OCCURRING RADIONUCLIDES IN BLAST FURNACE SLAG
(Radiation Protection Dosimetry (2012), pp. 1–7, 2012-07-22) Turhan, Şeref; Uğur, F.A.; Şahan, H.; Gören, E.; Gezer, F.; Yeğingil, Z.
The activity level and possible radiological impacts of naturally occurring radionuclides on the health of workers and members of the public, as a result of utilisation of blast furnace slag (BFS) samples as a substitute for aggregate in road construction were investigated by using a gamma-ray spectrometer and potential exposure scenarios given in Radiation Protection 122. The mean activity concentrations of the 226Ra, 232Th and 40K in BFS samples were found to be 152.4, 54.9 and 183.1 Bq kg21, respectively. These values are compared with typical values measured in BFS samples from the European Union countries, which are 270, 70 and 240 Bq kg21 for 226Ra, 232Th and 40K, respectively. The values of radium equivalent activity index calculated for BFS samples were within the recommended safety limits. The highest total annual effective doses evaluated as 0.9 and 0.4 mSv y21 for members of the public and workers, respectively, were lower than the annual limit of 1 mSv y21.
J Radioanal Nucl Chem (2014) 299:1427–1431
(J Radioanal Nucl Chem (2014) 299:1427–1431, 2014) Turhan, Şeref; Gören, E.; Uğur, F.A.; Gezer, F.; Özdemir, B.; Ufuktepe, Y.
Tritium activity in potable drinking water samples from Adana city were measured using liquid scintillation counting after distillation procedure. The results exposed that the activity concentrations of the tritium measured in one-third of these samples were lower than minimum detectable activity which has a value of 2 Bq/L for counting time of 1,500 min. However, the maximum and mean value of the tritium activity was found to be 9.1 Bq/L (77.3 TU) and 7.0 Bq/l (59.4 TU), respectively. These values were substantially below the 100 Bq/L which is normative limit in Turkey for waters intended for human consumption. The highest values of annual effective dose received by infants, children and adults due to measured tritium activity were estimated as 0.041, 0.057 and 0.120 lSv/y, respectively.
Tritium activity levels in drinking water of Adana, Turkey
(J Radioanal Nucl Chem (2014) 299:1427–1431, 2014-01-23) Turhan, Şeref; Gören, E.; Uğur, F.A.; Gezer, F.; Özdemir, B.; Ufuktepe, Y.
Tritium activity in potable drinking water samples from Adana city were measured using liquid scintillation counting after distillation procedure. The results exposed that the activity concentrations of the tritium measured in one-third of these samples were lower than minimum detectable activity which has a value of 2 Bq/L for counting time of 1,500 min. However, the maximum and mean value of the tritium activity was found to be 9.1 Bq/L (77.3 TU) and 7.0 Bq/l (59.4 TU), respectively. These values were substantially below the 100 Bq/L which is normative limit in Turkey for waters intended for human consumption. The highest values of annual effective dose received by infants, children and adults due to measured tritium activity were estimated as 0.041, 0.057 and 0.120 lSv/y, respectively.