Ядерна фізика та енергетика Nuclear Physics and Atomic Energy   ISSN: 1818-331X (Print), 2074-0565 (Online)   Publisher: Institute for Nuclear Research of the National Academy of Sciences of Ukraine   Languages: Ukrainian, English, Russian   Periodicity: 4 times per year   Open access peer reviewed journal

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V. I. Gulik^*

Institute for Safety Problems of Nuclear Power Plants, National Academy of Sciences of Ukraine, Kyiv, Ukraine

^*Corresponding author. E-mail address: volodymyr_gulik@ukr.net

Abstract: Calculation model developed by means of Monte Carlo code MCNP 4c for ⁶⁰Со gamma-irradiation source is presented. The simulation of gamma-ray transport in the developed model was carried out. Gamma-ray absorbed doses for different dwell positions were calculated. The distribution of the absorbed dose depending on the location of the material in the cell for irradiation is presented. The use of Monte Carlo simulation for control and verification of gamma-ray irradiation has been recommended for industrial gamma-ray sterilization facilities.

Keywords: ionizing radiation, radiation sterilization, Monte Carlo method, absorbed dose, dose mapping.

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