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Comparative Study Between Geant4, MCNP6 and Experimental Results Against Gamma Radiation Comes from a Cobalt-60 Source

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Abstract

The simulation codes based on the monte Carlo method are sophisticated averages and have become essential for dosimetry and radiation protection calculations close to the installations that handle radioactive sources. However, before starting to exploit these codes, they must be validated. The aim of this work is to validate two from the Monte Carlo simulation codes most used currently in the world , GEANT4 and MCNP6, for future use in dosimetry and radiation protection requirements in the BOukhalef Ionization Station (SIBO)/ Tangier, Morocco which manipulates a radioactive source of cobalt-60. The validation method is based on a comparison between the simulated results and those obtained by a Fricke system. The codes are well validated, indeed the simulation and experimental results were in good agreement.

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Authors and Affiliations

  1. Nuclear Engineering Group, LISTA Laboratory, Department of Physics, Faculty of Science Dhar El Mahraz, University Sidi Mohamed Ben Abdellah, City Fez, Morocco

    Y. El-Ouardi, A. Dadouch & A. Maghnouj

  2. Department of Physics, Faculty of Science, University of Ibn Tofail, Kenitra, Morocco

    A. Aknouch

  3. National Institute for Agronomical Research (INRA), Regional Center of Tangier, Irradiation Facility of Boukhalef (SIBO), Tangier, Morocco

    M. Mouhib

  4. Department of Physics, Faculty of Sciences, University of Mohammed Ist, Oujda, Morocco

    A. Didi

Authors
  1. Y. El-Ouardi
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  2. A. Dadouch
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  3. A. Aknouch
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  4. M. Mouhib
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  5. A. Maghnouj
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  6. A. Didi
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Corresponding author

Correspondence to Y. El-Ouardi.

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El-Ouardi, Y., Dadouch, A., Aknouch, A. et al. Comparative Study Between Geant4, MCNP6 and Experimental Results Against Gamma Radiation Comes from a Cobalt-60 Source. Moscow Univ. Phys. 75, 507–511 (2020). https://doi.org/10.3103/S0027134920050033

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  • DOI: https://doi.org/10.3103/S0027134920050033

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