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Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source

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Abstract

To check the dose uniformity and to determine the efficiency of medical devices sterilization by gamma irradiation after three half lives of the source, calculations of the absorbed dose were carried out. Monte Carlo simulations and dosimetry measurements, were established to study the radiation processing quality control. An isodose chart was created by GEANT4 Monte Carlo code to evaluate the absorbed dose rate uniformity inside the irradiation room from the year of the installation until the year of the source reload. The dose uniformity ratio (DUR) is deduced from maximum and minimum experimental doses in medical devices after three half lives of the source.

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Acknowledgements

The authors would like to acknowledge all the staff of the Ionizing Radiation Unit for their availability and support of this work.

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Authors and Affiliations

  1. Tunisian Center for Nuclear Sciences and Technology, Technopark Sidi Thabet, 2020, Ariana, Tunisia

    Leila Ounalli, Arbi Mejri, Ammar Bouabidi & Nafaa Reguigui

  2. Laboratory on Energy and Matter for Nuclear Sciences Development, Technopark Sidi Thabet, 2020, Ariana, Tunisia

    Leila Ounalli

  3. Tunisian Higher Institute of Medical Technologies, 9 Rue Zouhair Essafi 1006 TUNIS, 1006, Tunis, Tunisia

    Maroua Bhar

  4. Faculty of Sciences of Tunis, Technopark Sidi Thabet, 2020, Ariana, Tunisia

    Kais Manai, Ammar Bouabidi & Shayma Mohamed Abdallah

  5. College of Science and Arts, University of Bisha, Bisha, Kingdom of Saudi Arabia

    Kais Manai

Authors
  1. Leila Ounalli
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  2. Maroua Bhar
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  3. Arbi Mejri
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  4. Kais Manai
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  5. Ammar Bouabidi
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  6. Shayma Mohamed Abdallah
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  7. Nafaa Reguigui
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Correspondence to Leila Ounalli.

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Ounalli, L., Bhar, M., Mejri, A. et al. Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source. NUCL SCI TECH 28, 133 (2017). https://doi.org/10.1007/s41365-017-0289-5

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  • DOI: https://doi.org/10.1007/s41365-017-0289-5

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