In this paper, we develop a three-dimensional configuration of the Tunisian Gamma
Irradiation Facility (TGIF) to determine the spatial distribution of gamma absorbed dose rates
in the irradiation area at the 60 Co source rack. The results are obtained by using the
MCNP6 code. Experimental measurements of the gamma absorbed dose rate are
performed in order to be compared with the calculated results. Two dosimetry systems are
employed to perform measurements: red and amber perpex and cellulose triacetate (CTA) …