Radiological Concentration Distribution of 131I, 132I, 133I, 134I, and 135I Due to a Hypothetical Accident of TRIGA Mark-II Research Reactor


The present work gives a methodology for assessing radiological concentration of 131I, 132I, 133I, 134I, and 135I due to a hypothetical accident of TRIGA Mark-II research Reactor at AERE, Savar, Bangladesh. The concentrations were estimated through different pathways like ingestion of vegetation, milk, and meat from air and ground deposition. The maximum air concentrations for all 16 directions were found at 110 m distance from the core of the reactor and it was found to be highest in the southern (S) direction. The maximum ground concentration occurred immediately just after the accident in different directions. In all pathways, the most concentration was found to be in S-direction. The concentrations in vegetation of 131I, 133I, 135I were significant, while no concentrations of 132I and 134I were observed. The concentration in vegetation for 131I was found to be highest than all other isotopes of iodine. The concentrations of 133I were found to be higher and concentrations of 134I were observed to be lower in both milk and meat compared to other radio isotopes of iodine. In the case of a radiological accident, the results of the present study will be a valuable guide for adopting radiological safety measures for radiation protection against the ingestion of vegetables, milk and meat from around the research reactor at AERE, Savar, Bangladesh.

Share and Cite:

M. Malek, K. Chisty and M. Rahman, "Radiological Concentration Distribution of 131I, 132I, 133I, 134I, and 135I Due to a Hypothetical Accident of TRIGA Mark-II Research Reactor," Journal of Modern Physics, Vol. 3 No. 10, 2012, pp. 1572-1585. doi: 10.4236/jmp.2012.310194.

Conflicts of Interest

The authors declare no conflicts of interest.


[1] International Atomic Energy Agency, Information to be Submitted in Support of Licensing Application for Nuclear Power Plants, “A Safety Guide,” Technical Report Series No. 50-SG-G2, Vienna, 1979.
[2] A. Ararkrog, “Global Radiological Impact of Nuclear Activities in the Former Soviet Union,” Proceedings of International Symposium on Environmental Impact of Radioactive Releases, Vienna, 8-12 May 1995.
[3] International Atomic Energy Agency, “Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases,” Safety Series No. 57, IAEA, Vienna, 1982.
[4] I. I. Kryshev, K. P. Makhonko, T. G. Sazykina, “Dose Assessment and Reconstruction in the Areas of Russia Contaminated after the Chernobyl Accident,” IAEA-TECDOC-755, pp. 105-114.
[5] International Atomic Energy Agency, “Generic Models for Use in Assessing the Impact of Discharge of Radioactive Substances to the Environment,” Safety Series No. 19, IAEA, Vienna, 2001.
[6] International Atomic Energy Agency, “Research Reactor Core Conversion Guidebook,” IAEA-TECDOC-643, 2, 1992.
[7] W. L. Woodruff, D. K. Warinner and J. E. Motas, “Research Reactor Core Conversion Guide Book,” IAEA-TECDOC-643, 2, 1992, pp. 155-178.
[8] H. Chember, “Introduction to Health Physics,” 3rd Edition, The MeGraw-Hill Companies Inc., New York, 1996.
[9] INTERATOM, Bergisch Glad Bach, Federal Republic of Germany, “Fundamental Calculation Model for the Determination of the Radiological Effects inside and outside the Research Reactor after Hypothetical Accidents with Release of High Amount of Fission Products from the Core, Research Reactor Core Conversion Guidebook,” IAEA-TECDOC-643, IAEA, Vienna 2, 1992, pp. 211- 232.
[10] H. Geiss, K. Nester, P. Thomas and K. J. Vogt, “In der Bundesrepublik Deutschland Experimental Ermittelte Ausbreitungsparameter Fuer 100 m Emissionshoehe,” Reps Juel-1707, KIK-3095, Kernforschungsanlage Kuelich/Kern-forschungsze-ntrum, Karlsruhe, 1981.
[11] K. J. Vogt and H. Geiss, “Neue Ausbreitungskoeffizienten Fuer 50 and 100 m Emissionshaoehe,” Internal Rep., Kernforschungsanlage, Juelich, 1980.
[12] W. Huebschmann, K. Nester, and P. Thomas, “Ausbreitungsparameter Fuer Emissionshoehe, von 160 m und 195 m,” Rep. KfK-2939, Kernforschungszentrum, Karlsruhe, 1980.
[13] National Council on Radiation Protection and Measurements, “Uncertainty in NCRP Screening Models Relating to Atmospheric Transport, Deposition, and Uptake by Humans,” NCRP Commentary No. 8, NCRP, Bethesda, 1993.
[14] National Council on Radiation Protection and Measurements, “Screening Techniques for Determining Compliance with Environmental Standards,” Releases of Radionucliders to the Atmosphere, NCRP Commentary No. 3, Revision Plus Addendum, NCRP, Bethesda, 1996.
[15] S. S. Raza, M. Iqbal, A. Salauddin, R. Avila and S. Pervez, Time-Integrated Thyroid Dose for Accidental Releases from Pakistan Research Reactor,” Journal of Radiological Protection, Vol. 24, No. 3, 2004, pp. 307-314. doi:10.1088/0952-4746/24/3/009
[16] M. Mizanur Rahaman, “Dose Assessment of a Contaminated Land Containing Radioactive Materials,” M.Phil Thesis, Bangladesh University of Engineering and Technology, Dhaka, 2003.

Copyright © 2021 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.