PL EN


Preferencje help
Widoczny [Schowaj] Abstrakt
Liczba wyników
Czasopismo
2015 | 60 | 4 | 951-958
Tytuł artykułu

The dose of gamma radiation from building materials and soil

Treść / Zawartość
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
The radioactivity of some structural building materials, rows, binders, and final construction products, originating from Serbia or imported from other countries, was investigated in the current study by using the standard HPGe gamma spectrometry. The absorbed dose in the air was computed by the method of buildup factors for models of the room with the walls of concrete, gas-concrete, brick and stone. Using the conversion coefficients obtained by interpolation of the International Commission on Radiobiological Protection (ICRP) equivalent doses for isotropic irradiation, the corresponding average indoor effective dose from the radiation of building materials of 0.24 mSv·y−1 was determined. The outdoor dose of 0.047 mSv·y−1 was estimated on the basis of values of the specific absorbed dose rates calculated for the radiation of the series of 238U, 232Th and 40K from the ground and covering materials. The literature values of the effective dose conversion coefficients for ground geometry were applied as well as the published data for content of the radionuclides in the soil.
Słowa kluczowe
Wydawca

Czasopismo
Rocznik
Tom
60
Numer
4
Strony
951-958
Opis fizyczny
Daty
wydano
2015-12-01
otrzymano
2015-04-02
zaakceptowano
2015-09-17
online
2015-12-30
Twórcy
autor
  • Institute of Occupational Health, Vojislava Ilića bb, 18000 Niš, Serbia
autor
  • Department of Physics, University of Niš, P. O. Box 224, 18000 Niš, Serbia
  • Faculty of Science, University of Kragujevac, 12 R. Domanovića Str., 34000 Kragujevac, Serbia, nikezic@kg.ac.rs
Bibliografia
  • 1. International Atomic Energy Agency. (2003). Guidelines for radioelement mapping using gamma ray spectrometry data. Vienna: IAEA. (IAEA-TECDOC-1363).
  • 2. Bell, K. G. (1963). Uranium in carbonate rocks. Geological Survey professional paper 474 - A. Geological Survey (U.S.).
  • 3. Egidi, P., & Hull, C. (1999). Naturally occurring and technologically enhanced naturally occurring radioactive material. In Producers, users and proposed regulations, PEP Course 1.A Notes, Health Physics Society, 32nd Midyear Topical Meeting, Albuquerque, New Mexico.
  • 4. Vesić, D. (1987). The gamma spectrometry determination of uranium, thorium and potassium in geologically defi ned samples. Doctoral dissertation, Faculty of Science, Belgrade, Serbia. (in Serbian).
  • 5. Nikezić, D. (1990). The contribution to the experimental and theoretical study of indoor irradiation of the population and individuals. Doctoral dissertation, Faculty of Science, Kragujevac, Serbia. (in Serbian).
  • 6. Pavlić, B., Čonkić, Lj., Bikit, I., Slivka, J., Krmar, M., & Žikić, N. (2000). Estimation of the indoor exposure to external radiation from natural radionuclides in building materials in Vojvodina. In Proceedings of the Fifth International Symposium and Exhibition on Environmental Contamination in Central and Eastern Europe. Prague.
  • 7. Popović, D., & Todorović, D. (2006). Radon indoor concentrations and activity of radionuclides in building materials in Serbia. Facta Universitatis, Series: Physics, Chemistry and Technology, 4, 11-20.
  • 8. Krstić, D., Nikezić, D., Stevanović, N., & Vučić, D. (2007). Radioactivity of some domestic and imported building materials from south eastern Europe. Radiat. Meas., 42, 1731-1736.[WoS]
  • 9. Ujić, P., Čeliković, I., Kandić, A., Vukanac, I., Đurašević, M., Dragosavac, D., & Žunić, Z. S. (2010). Internal exposure from building materials exhaling 222Rn and 220Rn as compared to external exposure due to their natural radioactivity content. Appl. Radiat. Isot., 68, 201-206.[WoS]
  • 10. Manić, V., Manić, G., Nikezic, D., & Krstic, D. (2012). Calculation of dose rate conversion factors for 238U, 232Th and 40K in concrete structures of various dimensions, with application to Niš, Serbia. Radiat. Prot. Dosim., 152, 361-368.[WoS]
  • 11. National Council on Radiation Protection and Measurements. (1994). Exposure of the population in the United States and Canada from natural background radiation. Bethesda, Maryland. (NCRP Report 94).
  • 12. United Nations Scientific Committee on Effects of Atomic Radiation. (2000). Sources, effects and risks of ionizing radiation. UNSCEAR 2000 Report. New York: United Nations.
  • 13. Nuclear Regulatory Commission, Environmental Protection Agency, Department of Energy. (2009). Multi-Agency radiation survey and assessment of materials and equipment (MARSAME). USA. (NUREG-1575, Suppl. 1, EPA 402-R-09-001, DOE/HS-0004).
  • 14. European Commission. (1999). Radiological protection principles concerning the natural radioactivity of building materials. Radiation Protection 112. Luxembourg: Office for Official Publications of the European Communities.
  • 15. Official Gazette of the Republic of Serbia. (2009). The law on protection against ionizing radiation and nuclear safety. Official Gazette of the Republic of Serbia no. 36/2009 of 15 May 2009. (in Serbian).
  • 16. The Radiation and Nuclear Safety Authority (STUK). (2010). The radioactivity of building materials and ash. (Guide ST 12.2). Helsinki.
  • 17. Koblinger, L. (1978). Calculation of exposure rates from gamma sources in walls of dwelling rooms. Health Phys., 34, 459-463.[Crossref]
  • 18. Risica, S., Bolzan, C., & Nuccetelli, C. (2001). Radioactivity in building materials: room model analysis and experimental methods. Sci. Total. Environ., 272, 119-126.
  • 19. Maduar, M. F., & Hiromoto, G. (2004). Evaluation of indoor gamma radiation dose in dwellings. Radiat. Prot. Dosim., 111, 221-228.
  • 20. Beck, H. L. (1975). The physics of environmental gamma radiation fi elds. In The natural radiation environment II. Oak Ridge: United States Atomic Energy Commission.
  • 21. Clouvas, A., Xanthos, S., Antonopoulos-Domis, M., & Silva, J. (2000). Monte Carlo calculation of dose conversion factors for external exposure to photon emitters in soil. Health Phys., 78, 295-302.
  • 22. Krstic, D., & Nikezic, D. (2010). Calculation of the effective dose from natural radioactivity in soil using MCNP code. Appl. Radiat. Isot., 68, 946-947.[WoS]
  • 23. The Agency for Protection against Ionizing Radiation and Nuclear Safety of Serbia. (2011). Report on the level of exposure of the population to ionizing radiation from the environment in the Republic of Serbia in 2010. Belgrade (in Serbian). Available from www. srbatom.gov.rs.
  • 24. Radiological Laboratory, Institute of Occupational Health “Niš”. (2012). Final report on monitoring the activities of radionuclides in the soil and the environment of the city of Nis for the period 2011/2012 year. For the Directorate for Economy, Sustainable Development and Environmental Protection of the city of Niš, Niš. (in Serbian).
  • 25. Hubbell, J. H. (1969). Photon cross sections, attenuation coeffi cients, and energy absorption coeffi cients from 10 keV to 100 GeV. National Bureau of Standards, Washington DC. (NSRDS-NBS 29).
  • 26. Harima, Y., Tanaka, S., Sakamoto, Y., & Hirayama, H. (1991). Development of new gamma-ray buildup factor and application to shielding calculations. J. Nucl. Sci. Technol., 28, 74-84.
  • 27. American National Standards Institute. American Nuclear Society. (1991). Gamma-ray attenuation coefficients and buildup factors for engineering materials. La Grange Park, Illinois, USA. (ANSI/ ANS-6.4.3-1991).
  • 28. Goldstein, H. (1959). Fundamental aspects of reactor shielding. Addison-Wesley Publishing Co; reprinted by Johnson Reprint Corp. (1971).
  • 29. Al-Jundi, J., Ulanovsky, A., & Prohl, G. (2009). Doses of external exposure in Jordan house due to gamma-emitting natural radionuclides in building materials. J. Environ. Radioact., 100, 841-846.[WoS]
  • 30. International Commission on Radiological Protection. (2007). The 2007 recommendations of the Commission on Radiological Protection. (ICRP Publication 103), Ann. ICRP.
  • 31. International Commission on Radiological Protection. (1996). Conversion coeffi cients for use in radiological protection against external radiation. (ICRP Publication 74). Oxford, UK: Pergamon Press.
  • 32. Zankl, M., Petoussi-Henß, N., Drexler, G., & Saito, K. (1997). The calculation of dose from external photon exposures using reference human phantoms and Monte Carlo methods Part VII: Organ doses due to parallel and environmental exposure geometries. Institut für Strahlenschutz. (GSF-Bericht 8/97).
  • 33. Lee, C., Lee, L., Han, E. Y., & Bolch, W. E. (2007). Consideration of the ICRP revised tissue weighting factors on age-dependent values of the effective dose for external photons. Phys. Med. Biol., 52, 41-58.[WoS]
  • 34. Manić, V., Nikezic, D., Krstic, D., & Manić, G. (2014). Assessment of indoor absorbed gamma dose rate from natural radionuclides in concrete by the method of build-up factors. Radiat. Prot. Dosim., 162(4), 609-617. DOI: 10.1093/rpd/nct358.[WoS][Crossref]
  • 35. Mustonen, R. (1984). Methods for evaluation of radiation from building materials. Radiat. Prot. Dosim., 7, 235-238.
  • 36. Unger, L. M., & Trubey, D. K. (1981). Specific gamma- ray dose constants for nuclides important to dosimetry and radiological assessment. Oak Ridge, Tennessee: Oak Ridge Laboratory. (ORNL/RSIC-45).
  • 37. Nuccetelli, C., Risica, S., D’Alessandro, M., & Trevisi, R. (2012). Natural radioactivity in building material in the European Union: robustness of the activity concentration index I and comparison with a room model. J. Radiol. Prot., 32, 349-358.[WoS][Crossref]
  • 38. Markkanen, M. (1995). Radiation dose assessments for materials with elevated natural radioactivity. Helsinki: Finnish Centre for Radiation and Nuclear Safety. (STUK-B-STO 32).
Typ dokumentu
Bibliografia
Identyfikatory
Identyfikator YADDA
bwmeta1.element.-psjd-doi-10_1515_nuka-2015-0148
JavaScript jest wyłączony w Twojej przeglądarce internetowej. Włącz go, a następnie odśwież stronę, aby móc w pełni z niej korzystać.