Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor

Nema Mohamed Kandil; Faten Salah Tawfik

doi:doi:10.11648/j.ijepp.20210903.12

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Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor

Nema Mohamed Kandil, Faten Salah Tawfik

Published in International Journal of Environmental Protection and Policy (Volume 9, Issue 3)

Received: 11 June 2021 Accepted: 26 June 2021 Published: 2 July 2021

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Abstract

Inshas site is very important site, it is considered as a first nuclear site in Egypt. It contains the first and the second research reactors and other important facilities such as the Egyptian Fuel Manufacturing Pilot Plant (FMPP) which submits the fuel to the second research reactors. The goals of this paper are to assess different emergency plan scenarios, determine the effects of metrological conditions on the dispersion of the radioactive plume, and calculate the overall effective dose equivalent values (TEDE). The meteorological parameters for one complete year 2020 (hourly) meteorological data were analysed in details such as wind direction, wind speed and temperature. The HotSpot code was used to model atmospheric dispersion and its application resulted in a radiation dose profile around the site using meteorological parameters specific to the area under study. This study used more than one scenario to investigate the role of various meteorological parameters. The radionuclide source term of Cs-137 was assumed to be 2.10E+15Bq. The results show that the maximum dose form all postulated scenarios is about 1.1E+4 Sv is observed at 10 m from the release source for weather stability class F, which is greater than the IAEA occupational exposure limit of 0.02 Sv per year. The results can also show that the time of accident is a major effect on the impact of accident and then on the consequences of emergency plan.

Published in	International Journal of Environmental Protection and Policy (Volume 9, Issue 3)
DOI	10.11648/j.ijepp.20210903.12
Page(s)	59-68
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2021. Published by Science Publishing Group

Keywords

Accidental Release, Radionuclides, Radioactive Contaminant, Gaussian Model, HOTSPOT

References

[1]	J. L. Muswema, G. B. Ekoko, V. M. Lukanda, J. K.-K. Lobo, E. O. Darko, E. K. Boafo. "Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa", Nuclear Engineering and Design, 2015.
[2]	Z. Foudil, B. Mohamed, and Z. Taher, Estimating of Core Inventory, Source Term and Doses Results for NUR Research Reactor under a Hypothetical Sever Accident ‘Progress in Nuclear Energy, Vol. 100, pp 365-372, 2017.
[3]	Raza, s. s., Iqbal, M., 2005. Atmospheric Dispersion Modeling for an Accident Release from the Pakistan Research Reactor -1 (PARR-1). Ann. Nucl. Energy 32, 1157.
[4]	Zeggar Foudila, Belgaid Mohamedb, and Zidi Taha Estimating of core inventory, source term and doses results for the NUR research reactor under a hypothetical severe accident, Volume 100, September 2017, Pages 365-372.
[5]	Safety Analysis Report of Egypt’s Second Research Reactor (ETRR-2), (1995).
[6]	IAEA, Derivation of the source term and analysis of the radiological consequences of research reactor accidents, safety reports series (2008). No. 53.
[7]	HOTSPOT Code Version 2.06. Developed at the Lawrence Livermore National Laboratory, University of California, USA, 2014.
[8]	Mariachiara Carestia1, Andrea Malizia1, Oscar Barlascini1, Eugenio Fiorini1, Paolo Maurizio Soave1, Gianna Latini, Orlando Cenciarelli1, Fabrizio D’Amico, Carlo Bellecci1, Pasquale Gaudio1 USE of the “HotSpot” Code for Safety and Security Analysis In Nuclear Power Plants: A Case Study. April 2016, Vol. 15.
[9]	International Commission on Radiological Protection (ICRP), Basis for Doisimetric Quantities Used in Radiological Protection. ICRP, Ottawa, Canada, 2005.
[10]	Steven, G. M, HotSpot, Health Physics Codes, Version 2.07.1, User's Guide. National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory, Livermore, CA 94550, 2010.
[11]	Homann S. G. and Aluzzi F. HotSpot Health Physics Codes Version 3.0 User's Guide. National Atmospheric Release Advisory Center Lawrence Livermore. National Laboratory Livermore, CA 94550, 2013.
[12]	Ned Xoubi. "Assessment of environmental radioactive surface contamination from a hypothetical nuclear research reactor accident", Heliyon, 2020.
[13]	Rentai, Y. Atmospheric dispersion of radioactive material in radiological risk assessment and emergency response. Progress in Nuclear Science and Technology, Vol. 1, 2011, pp. 7-13.
[14]	Van Dop, H., Atmospheric Distribution of Pollutants and Modelling of Air Pollution Dispersion, in Air Pollution. 1986, Springer Berlin Heidelberg: Berlin, Heidelberg. p. 107-147.

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APA Style

Nema Mohamed Kandil, Faten Salah Tawfik. (2021). Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. International Journal of Environmental Protection and Policy, 9(3), 59-68. https://doi.org/10.11648/j.ijepp.20210903.12

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ACS Style

Nema Mohamed Kandil; Faten Salah Tawfik. Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. Int. J. Environ. Prot. Policy 2021, 9(3), 59-68. doi: 10.11648/j.ijepp.20210903.12

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AMA Style

Nema Mohamed Kandil, Faten Salah Tawfik. Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. Int J Environ Prot Policy. 2021;9(3):59-68. doi: 10.11648/j.ijepp.20210903.12

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@article{10.11648/j.ijepp.20210903.12,
  author = {Nema Mohamed Kandil and Faten Salah Tawfik},
  title = {Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor},
  journal = {International Journal of Environmental Protection and Policy},
  volume = {9},
  number = {3},
  pages = {59-68},
  doi = {10.11648/j.ijepp.20210903.12},
  url = {https://doi.org/10.11648/j.ijepp.20210903.12},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepp.20210903.12},
  abstract = {Inshas site is very important site, it is considered as a first nuclear site in Egypt. It contains the first and the second research reactors and other important facilities such as the Egyptian Fuel Manufacturing Pilot Plant (FMPP) which submits the fuel to the second research reactors. The goals of this paper are to assess different emergency plan scenarios, determine the effects of metrological conditions on the dispersion of the radioactive plume, and calculate the overall effective dose equivalent values (TEDE). The meteorological parameters for one complete year 2020 (hourly) meteorological data were analysed in details such as wind direction, wind speed and temperature. The HotSpot code was used to model atmospheric dispersion and its application resulted in a radiation dose profile around the site using meteorological parameters specific to the area under study. This study used more than one scenario to investigate the role of various meteorological parameters. The radionuclide source term of Cs-137 was assumed to be 2.10E+15Bq. The results show that the maximum dose form all postulated scenarios is about 1.1E+4 Sv is observed at 10 m from the release source for weather stability class F, which is greater than the IAEA occupational exposure limit of 0.02 Sv per year. The results can also show that the time of accident is a major effect on the impact of accident and then on the consequences of emergency plan.},
 year = {2021}
}

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TY  - JOUR
T1  - Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor
AU  - Nema Mohamed Kandil
AU  - Faten Salah Tawfik
Y1  - 2021/07/02
PY  - 2021
N1  - https://doi.org/10.11648/j.ijepp.20210903.12
DO  - 10.11648/j.ijepp.20210903.12
T2  - International Journal of Environmental Protection and Policy
JF  - International Journal of Environmental Protection and Policy
JO  - International Journal of Environmental Protection and Policy
SP  - 59
EP  - 68
PB  - Science Publishing Group
SN  - 2330-7536
UR  - https://doi.org/10.11648/j.ijepp.20210903.12
AB  - Inshas site is very important site, it is considered as a first nuclear site in Egypt. It contains the first and the second research reactors and other important facilities such as the Egyptian Fuel Manufacturing Pilot Plant (FMPP) which submits the fuel to the second research reactors. The goals of this paper are to assess different emergency plan scenarios, determine the effects of metrological conditions on the dispersion of the radioactive plume, and calculate the overall effective dose equivalent values (TEDE). The meteorological parameters for one complete year 2020 (hourly) meteorological data were analysed in details such as wind direction, wind speed and temperature. The HotSpot code was used to model atmospheric dispersion and its application resulted in a radiation dose profile around the site using meteorological parameters specific to the area under study. This study used more than one scenario to investigate the role of various meteorological parameters. The radionuclide source term of Cs-137 was assumed to be 2.10E+15Bq. The results show that the maximum dose form all postulated scenarios is about 1.1E+4 Sv is observed at 10 m from the release source for weather stability class F, which is greater than the IAEA occupational exposure limit of 0.02 Sv per year. The results can also show that the time of accident is a major effect on the impact of accident and then on the consequences of emergency plan.
VL  - 9
IS  - 3
ER  -

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Author Information

Nema Mohamed Kandil

Nuclear & Radiological Regulatory Authority (NRRA), Cairo, Egypt
Faten Salah Tawfik

Nuclear & Radiological Regulatory Authority (NRRA), Cairo, Egypt

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APA Style

Nema Mohamed Kandil, Faten Salah Tawfik. (2021). Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. International Journal of Environmental Protection and Policy, 9(3), 59-68. https://doi.org/10.11648/j.ijepp.20210903.12

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ACS Style

Nema Mohamed Kandil; Faten Salah Tawfik. Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. Int. J. Environ. Prot. Policy 2021, 9(3), 59-68. doi: 10.11648/j.ijepp.20210903.12

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AMA Style

Nema Mohamed Kandil, Faten Salah Tawfik. Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor. Int J Environ Prot Policy. 2021;9(3):59-68. doi: 10.11648/j.ijepp.20210903.12

Copy | Download

@article{10.11648/j.ijepp.20210903.12,
  author = {Nema Mohamed Kandil and Faten Salah Tawfik},
  title = {Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor},
  journal = {International Journal of Environmental Protection and Policy},
  volume = {9},
  number = {3},
  pages = {59-68},
  doi = {10.11648/j.ijepp.20210903.12},
  url = {https://doi.org/10.11648/j.ijepp.20210903.12},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepp.20210903.12},
  abstract = {Inshas site is very important site, it is considered as a first nuclear site in Egypt. It contains the first and the second research reactors and other important facilities such as the Egyptian Fuel Manufacturing Pilot Plant (FMPP) which submits the fuel to the second research reactors. The goals of this paper are to assess different emergency plan scenarios, determine the effects of metrological conditions on the dispersion of the radioactive plume, and calculate the overall effective dose equivalent values (TEDE). The meteorological parameters for one complete year 2020 (hourly) meteorological data were analysed in details such as wind direction, wind speed and temperature. The HotSpot code was used to model atmospheric dispersion and its application resulted in a radiation dose profile around the site using meteorological parameters specific to the area under study. This study used more than one scenario to investigate the role of various meteorological parameters. The radionuclide source term of Cs-137 was assumed to be 2.10E+15Bq. The results show that the maximum dose form all postulated scenarios is about 1.1E+4 Sv is observed at 10 m from the release source for weather stability class F, which is greater than the IAEA occupational exposure limit of 0.02 Sv per year. The results can also show that the time of accident is a major effect on the impact of accident and then on the consequences of emergency plan.},
 year = {2021}
}

Copy | Download

TY  - JOUR
T1  - Evaluation of Radiation Doses for Hypothetical Accident Scenarios of Egyptian Second Research Reactor
AU  - Nema Mohamed Kandil
AU  - Faten Salah Tawfik
Y1  - 2021/07/02
PY  - 2021
N1  - https://doi.org/10.11648/j.ijepp.20210903.12
DO  - 10.11648/j.ijepp.20210903.12
T2  - International Journal of Environmental Protection and Policy
JF  - International Journal of Environmental Protection and Policy
JO  - International Journal of Environmental Protection and Policy
SP  - 59
EP  - 68
PB  - Science Publishing Group
SN  - 2330-7536
UR  - https://doi.org/10.11648/j.ijepp.20210903.12
AB  - Inshas site is very important site, it is considered as a first nuclear site in Egypt. It contains the first and the second research reactors and other important facilities such as the Egyptian Fuel Manufacturing Pilot Plant (FMPP) which submits the fuel to the second research reactors. The goals of this paper are to assess different emergency plan scenarios, determine the effects of metrological conditions on the dispersion of the radioactive plume, and calculate the overall effective dose equivalent values (TEDE). The meteorological parameters for one complete year 2020 (hourly) meteorological data were analysed in details such as wind direction, wind speed and temperature. The HotSpot code was used to model atmospheric dispersion and its application resulted in a radiation dose profile around the site using meteorological parameters specific to the area under study. This study used more than one scenario to investigate the role of various meteorological parameters. The radionuclide source term of Cs-137 was assumed to be 2.10E+15Bq. The results show that the maximum dose form all postulated scenarios is about 1.1E+4 Sv is observed at 10 m from the release source for weather stability class F, which is greater than the IAEA occupational exposure limit of 0.02 Sv per year. The results can also show that the time of accident is a major effect on the impact of accident and then on the consequences of emergency plan.
VL  - 9
IS  - 3
ER  -

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