Home Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
Article
Licensed
Unlicensed Requires Authentication

Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey

  • C. Eke and I. Boztosun
Published/Copyright: June 26, 2015
Become an author with De Gruyter Brill
Submit Manuscript Author Information
Kerntechnik
From the journal Kerntechnik Volume 80 Issue 3

Abstract

In this paper, we attempt to determine the activity concentration of natural and artificial radionuclides in 37 sand samples from the Mediterranean coast of Antalya in Turkey by using a high purity Germanium (HpGe) detector. 238U, 232Th, 40K and 137Cs activity concentrations, absorbed dose rate, annual effective dose equivalent, radium equivalent activity, external and internal hazard index of sand samples are determined res-pectively. The average values are 13.43 ± 0.21 Bq/kg, 6.96 ± 0.06 Bq/kg and, 122.46 ± 18.58 Bq/kg, for 238U, 232Th and 40K respectively. Most of the activity concentration values are less than below minimum detection limit for 137Cs. The average values of the absorbed dose rate D (nGy/h), annual effective dose equivalent AEDE(μSv/y), radium equivalent activity Raeq (Bq/kg), external hazard index Hex and internal hazard index Hin are 15.52 nGy/h, 19.03 μSv/y, 32.81 Bq/kg, 0.09 and 0.12 respectively. It is observed that 238U, 232Th, 40K and 137Cs activity concentrations, absorbed dose rate, annual effective dose equivalent, radium equivalent activity are in the limit of the published values, external and internal hazard index values are less than unity.

Kurzfassung

In diesem Beitrag wird die Aktivitätskonzentration von natürlichen und künstlichen Radionukliden in 37 Sandproben von der mediterranen Küste in Antalya mit Hilfe eines hoch-reinen Germanium (HpGe) Detectors bestimmt. 238U, 232Th, 40K und 137Cs-Aktivitätskonzentrationen, absorbierte Dosisleistung, jährliche effektive Äquivalentdosis, Radium-Äquivalent-Aktivität der Sandproben wurden bestimmt. Die Durchschnittswerte sind 13.43 ± 0.21 Bq/kg, 6.96 ± 0.06 Bq/kg und 122.46 ± 18.58 Bq/kg für 238U, 232Th und 40K. Die Werte der meisten Aktivitätskonzentrationen liegen unter der Nachweisgrenze für 137Cs. Die Durchschnittswerte der Dosisleistung D (nGy/h), der jährlichen effektiven Äquivalentdosis AEDE(μSv/y), der Radium-Äquivalent-Aktivität Raeq (Bq/kg), des externen Gefahrenindex Hex und des internen Gefahrenindex Hin liegen bei 15.52 nGy/h, 19.03 μSv/y, 32.81 Bq/kg, 0.09 and 0.12. Es wird beobachtet, dass 238U, 232Th, 40K und 137Cs-Aktivitätskonzentrationen, absorbierte Dosisleistung, jährliche effektive Äquivalentdosis, Radium-Äquivalent-Aktivität unter den Grenzwerten für die Bevölkerung liegen, die Werte für den externer und internen Gefahrenindex unter Eins.

* Corresponding Author: E-mail:

References

1 Agbalagba, E. O.; Avwiri, G. O.; Chad-Umoreh, Y. E.: γ-Spectroscopy measurement of natural radioactivity and assessment of radiation hazard indices in soil samples from oil fields environment of Delta State Nigeria. J Environ Radioact.109 (2012) 64–7010.1016/j.jenvrad.2011.10.012Search in Google Scholar

2 Kabir, K. A.; Islam, S. M. A.; Rahman, M. M.: Distribution of radionuclides in surface soil and bottom sediment in the district of Jessore, Bangladesh and evaluation of radiation hazard. J Bangladesh Acad Sci33 (2009) 117–130Search in Google Scholar

3 Alencar, A. S.; Freitas, A. C.: Reference levels of natural radioactivity for the beach sands in a Brazilian southeastern coastal region. Radiat Meas.40 (2005) 76–8310.1016/j.radmeas.2004.08.003Search in Google Scholar

4 UNSCEAR: United Nations Scientific Committee on the Effect of Atomic Radiation. Sources and Effects of Ionizing Radiation. Report to General Assembly, with Scientific Annexes, NewYork, United Nations, 2000Search in Google Scholar

5 Alaamer, A. S.: Assessment of human exposures to natural sources of radiation in soil of Riyadh, Saudi Arabia. Turkish J Eng Env Sci.32 (2008) 229–234Search in Google Scholar

6 Mohanty, A. K.; Sengupta, D.; Das, S. K.; Saha, S. K.; Van, K. V.: Natural radioactivity and radiation exposure in the high background area at Chhatrapur beach placer deposit of Orissa, India. J Environ Radioact.75 (2004a) 15–3310.1016/j.jenvrad.2003.09.004Search in Google Scholar

7 Kannan, V.; Rajan, M. P.; Iyengar, M. A. R.; Ramesh, R.: Distribution of natural and anthropogenic radionuclides in soil and beach sand sample of Kalpakkam (India) using hyper pure germanium (HPGe)gamma ray spectrometry. Appl Radiat Isot.57 (2002) 109–11910.1016/S0969-8043(01)00262-7Search in Google Scholar

8 Mohanty, A. K.; Sengupta, D.; Das, S. K.; Vijayan, V.; Saha, S. K.: Natural radioactivityin the newly discovered high background radiation area on the eastern coast of Orissa, India. Radiat Meas.38 (2004b) 153–16510.1016/j.radmeas.2003.08.003Search in Google Scholar

9 Aboelkhair, H.; Zaaeimah, M.: Potential of natural gamma-ray spectrometry for mapping and environmental monitoring of black-sand beach deposits on the northern coast of Sinai, Egypt. Radiat Prot Dosim.154 (2013) 81–9410.1093/rpd/ncs136Search in Google Scholar PubMed

10 Lu, X.; Zhang, X.: Measurement of natural radioactivity in beach sands from Rizhao bathing beach, China. Radiat Prot Dosim.130 (2008) 385–38810.1093/rpd/ncn053Search in Google Scholar PubMed

11 Withanage, A. P.; Mahawatte, P.: Radioactivity of beach sand in the south western coast of Sri Lanka. Radiat Prot Dosim.153 (2013) 384–38910.1093/rpd/ncs107Search in Google Scholar PubMed

12 Qureshi, A. A.; Ali, M.; Waheed, A.; Manzoor, S.; Siddique, R. U. H.; Khan, H. A.: Assessment of radiological hazards of Lawrencepur Sand, Pakistan using gamma spectrometry. Radiat Prot Dosim.157 (2013) 73–8410.1093/rpd/nct105Search in Google Scholar PubMed

13 Arnedo, M. A.; Tejera, A.; Rubiano, J. G.; Alonso, H.; Gil, J. M.; Rodriguez, R.; Martel, P.: Natural radioactivity measurements of beach sands in Gran Canaria, Canary Islands (Spain). Radiat Prot Dosim.156 (2013) 75–8610.1093/rpd/nct044Search in Google Scholar PubMed

14 Freitas, A. C.; Alencar, A. S.: Gamma dose rates and distribution of natural radionuclides in sand beaches Ilha Grande, Southeastern Brazil. J Environ Radioact.75 (2004) 211–22310.1016/j.jenvrad.2004.01.002Search in Google Scholar PubMed

15 Uosif, M. A. M.; El-Taher, A.; Abbady, A. G. E.: Radiological significance of beach sand used for climatotherapy from Safaga,Egypt. Radiat Prot Dosim.131 (2008) 331–33910.1093/rpd/ncn175Search in Google Scholar PubMed

16 Ramasamy, V.; Sundarrajan, M.; Paramasivam, K.; Meenakshisundaram, V.; Suresh, G.: Assessment of spatial distribution and radiological hazardous nature of radionuclides in high background radiation area, Kerala, India. Appl Radiat Isot.73 (2013) 21–3110.1016/j.apradiso.2012.11.014Search in Google Scholar PubMed

17 Antovic, N. M.; Svrkota, N.; Antovic, I.; Svrkota, R.; Jancic, D.: Radioactivity in Montenegro beach sands and assessment of the corresponding environmental risk. Isot Environ Health Stud.49 (2013) 153–16210.1080/10256016.2013.734303Search in Google Scholar PubMed

18 Korkulu, Z.; Ozkan, N.: Determination of natural radioactivity levels of beach sand samples in the black sea coast of Kocaeli (Turkey). Radiat Phys Chem.88 (2013) 27–3110.1016/j.radphyschem.2013.03.022Search in Google Scholar

19 Aykamis, A. S.; Kilic, M.: Natural radionuclide distribution in quartzite sands of East Mediterranean Region (Turkey). Bull Eng Geol Environ.70 (2011) 317–32110.1007/s10064-010-0319-6Search in Google Scholar

20 Cevik, U.; Damla, N.; Kobya, A. I.; Celik, N.; Celik, A.; Van, A. A.: Assessment of natural radioactivity of sand used in Turkey. J Radiol Prot.29 (2009) 61–7410.1088/0952-4746/29/1/004Search in Google Scholar PubMed

21 Orgun, Y.; Altinsoy, N.; Sahin, S. Y.; Gungor, Y.; Gultekin, A. H.; Karahan, G.; Karacik, Z.: Natural and antropogenic radionuclides in rocks and beach sands from Ezine region (Çanakkale) Western Anatolia, Turkey. Appl Radiat Isot.65 (2007) 739–74710.1016/j.apradiso.2006.06.011Search in Google Scholar PubMed

22 Eke, C.; Boztosun, I.: Gamma-ray spectrometry for the self-attenuation correction factor of the sand samples from Antalya in Turkey. J. Radioanal Nucl Chem.301 (2014) 103–10810.1007/s10967-014-3145-7Search in Google Scholar

23 Agar, O.; Boztosun, I.; Korkmaz, M. E.; Ozmen, S. F.: Measurement of radioactivity levels and assessment of radioactivity hazards of soil samples in Karaman, Turkey. Radiat Prot Dosim (2014) 10.1093/rpd/ncu027Search in Google Scholar PubMed

24 Ozmen, S. F.; Boztosun, I.; Yavuz, M.; Tunc, M. R.: Determination of gamma radioactivity levels and associated dose rates of soil samples of the Akkuyu/Mersin using high-resolution gamma-ray spectrometry. Radiat Prot Dosim.158 (2014) 461–46510.1093/rpd/nct267Search in Google Scholar

25 Maestro-32: Multi-channel analyser software, A65-B32 model, Ortec, 2008Search in Google Scholar

26 Al-Masri, M. S.; Hasan, M.; Al-Hamwi, A.; Amin, Y.; Doubal, A. W.: Mass attenuation coefficients of soil and sediment samples using gamma energies from 46.5 to 1332 keV. J Environ Radioact.116 (2013) 28–3310.1016/j.jenvrad.2012.09.008Search in Google Scholar

27 Cutshall, N. H.; Larsen, I. L.; Olsen, C. R.: Direct analysis of 210Pb in sediment samples: self absorption corrections. Nucl Instrum Meth.206 (1983) 309–31210.1016/0167-5087(83)91273-5Search in Google Scholar

28 Beretka, J.; Mathew, P. J.: Natural radioactivity of Australian building materials, industrial wastes and by-products. Health Phys.48 (1985) 87–9510.1097/00004032-198501000-00007Search in Google Scholar PubMed

29 Ravisankar, R.; Vanasundari, K.; Chandrasekaran, A.; Rajalakshmi, A.; Suganya, M.; Vijayagopal, P.; Meenakshisundaram, V.: Measurement of natural radioactivity in building materials of Namakkal, Tamil Nadu, India using gamma-ray spectrometry. Appl Radiat Isot.70 (2012) 699–70410.1016/j.apradiso.2011.12.001Search in Google Scholar PubMed

30 SPSS (2008): SPSS (Statistical Package for the Social Sciences) for windows, version 17.0. Chicago: SPSS Inc.Search in Google Scholar

31 NEA-OECD: Exposure to natural radioactivity in building materials. Report by NEA group of Experts of the nuclear energy agency, OECD, Paris, France, 1979Search in Google Scholar

Received: 2015-01-05
Published Online: 2015-06-26
Published in Print: 2015-07-25

© 2015, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved data evaluation methodology for energy ranges with missing experimental data
  7. Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
  8. Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
  9. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
  10. Development of a hydrogen diffusion gothic model of MARK III-containment
  11. Analysis of safety parameters for the MINERVE reactor
  12. Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
  13. Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
  14. Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
  15. Study of 60Co as gamma source in backscatter gamma densitometers
  16. Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
  17. Technical Notes
  18. Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
https://doi.org/10.3139/124.110474

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved data evaluation methodology for energy ranges with missing experimental data
  7. Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
  8. Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
  9. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
  10. Development of a hydrogen diffusion gothic model of MARK III-containment
  11. Analysis of safety parameters for the MINERVE reactor
  12. Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
  13. Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
  14. Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
  15. Study of 60Co as gamma source in backscatter gamma densitometers
  16. Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
  17. Technical Notes
  18. Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
Sign up now to receive a 20% welcome discount
Institutional Access
How does access work?
Have an idea on how to improve our website?
Please write us.
© 2025 De Gruyter Brill
Downloaded on 6.10.2025 from https://www.degruyterbrill.com/document/doi/10.3139/124.110474/html?lang=en
Scroll to top button