Comparative Study Between Geant4, MCNP6 and Experimental Results Against Gamma Radiation Comes from a Cobalt-60 Source
Youssef El-ouardi, Ahmed Dadouch, Adil Aknouch, Mohammed Mouhib, Abdelmajid Maghnouj, Abdessamad Didi
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.