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Assessment of Radiological Dose around a 3-MW TRIGA Mark-II Research Reactor

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Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
A hypothetical accidental case of a 3-MW TRIGA Mark-II research reactor has been assumed to assess the radiological consequences due to the deposition of 137Cs and 90Sr on ground, vegetation, milk and meat. The air concentrations in sixteen cardinal directions have been estimated where the maximum concentration has been found to be at 110 m distance from the core of the reactor for all the directions. Calculated maximum doses of 137Cs, 90Sr and both 137Cs and 90Sr have been found to be within the ranges of 0.005-0.014 μSv hr–1, 0.013-0.036 μSv hr–1 and 0.018-0.05 μSv hr–1, respectively for all the directions, which are below the measured background dose limit 0.25 μSv hr–1 and also within the IAEA acceptable dose rate limit of 0.5 μSv hr–1. The calculated low doses due to the aforementioned radionuclides can be considered negligible with regard to the radiation hazards. The relationship between total effective dose rate for various pathways (i.e. immersion, inhalation, ground deposition, and ingestion of contaminated vegetation, milk, meat) and air concentration in all the directions has been established. Obtained relation reveals that the total effective dose rate is directly proportional to the air concentration, and the overall proportionality constants for 137Cs and 90Sr radionuclides have been obtained as 0.57 and 0.28, respectively. This study might provide information on the radiological safety required for the radiation protection purposes of the people living in the vicinity of the reactor site.
Rocznik
Strony
183--200
Opis fizyczny
Bibliogr. 12 poz., rys., wykr.
Twórcy
  • Health Physics and Radioactive Waste Management Unit, Institute of Nuclear Science and Technology, AERE, Savar, Dhaka - 1349, Bangladesh
  • Health Physics and Radioactive Waste Management Unit, Institute of Nuclear Science and Technology, AERE, Savar, Dhaka - 1349, Bangladesh
autor
  • Health Physics and Radioactive Waste Management Unit, Institute of Nuclear Science and Technology, AERE, Savar, Dhaka - 1349, Bangladesh
autor
  • Health Physics and Radioactive Waste Management Unit, Institute of Nuclear Science and Technology, AERE, Savar, Dhaka - 1349, Bangladesh
autor
  • Health Physics Division, Atomic Energy Centre, Ramna, Dhaka - 1000, Bangladesh
  • Department of Physics, Jahangirnagar University, Savar, Dhaka - 1342, Bangladesh
  • Department of Physics, Jahangirnagar University, Savar, Dhaka - 1342, Bangladesh
  • Department of Physics, University of Chittagong, Chittagong - 4331, Bangladesh
Bibliografia
  • [1] Merril Eisenbud, Environmental Radioactivity, Chap. 5, pp. 118-136, Academic Press, New York, 1973.
  • [2] Rosalie Berlell, No Immediate Danger: Prognosis for a Radioactive Earth, (ISBN 0-913990-25-2), 2000, pages 15-63.
  • [3] D. McCurdy, L-Q. Tai, S. Frias, Z. Wang, Radiation Research 147(1) (1997) 48-54.
  • [4] Z. S. Beauvais, K. H. Thompson, K. J. Kearfott, Health Physics 97(1) (2009) 50-67.
  • [5] International Atomic Energy Agency, Generic Procedures for Assessment and Response during a Radiological Emergency, IAEA-TECDOC-1162, IAEA,Vienna, (2000).
  • [6] International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, SRS No. 57, 1982.
  • [7] International Atomic Energy Agency, Generic Models for Use in Assessing the Impact of Discharges of Radioactive Substances to the Environment, Safety Series No19, IAEA, Vienna 2001.
  • [8] W. L. Woodruff, D. K. Warinner, J. E. Matos, Radiological Consequence Analysis, Research Reactor Core Conversion Guidebook, IAEA-TECDOC- 643, Vol. 2, pp. 155-178, IAEA, Vienna, 1992.
  • [9] J. N. Anoussis, N. G. Chrysochoides, Estimation of Radiological Doses from Research Reactor Accidents, International Atomic Energy Agency, Research Reactor Core Conversion Guidebook, IAEA TECDOC- 643, Vol. 2, pp. 185-200, IAEA, Vienna,1992.
  • [10] INTERATOM, Bergisch Gladbach, Federal Republic of Germany; Fundamental Calculation Model for the Determination of the Radiological Effects, Inside and Outside A Research Reactor, After Hypothetical Accidents, With Release of High Amount of Fission Products From the Core; Research Reactor Core Conversion Guidebook, IAEA-TECDOC-643, Vol. 2, pp. 211 – 232, IAEA, Vienna, (1992).
  • [11] Herman Cember, Thomas E. Johnson, Introduction to Health Physics, Fourth Edition, page no. 609, The McGraw-Hill Companies Inc., 2009.
  • [12] International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series No. 115, IAEA, Vienna (1996).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-ed876365-cad1-4139-8af0-efd0f8312598
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