Dose mapping simulation using the MCNP code for the Syrian gamma irradiation facility and benchmarking

摘要

A three dimensional model for the Syrian gamma irradiation facility (SG1F) is developed in this paper to calculate the gamma ray dose rate spatial distribution in the irradiation room at the ~(60)Co source board using the MCNP-4C code. Measurement of the gamma ray dose rate spatial distribution using the Chlo-robenzene dosimeter is conducted as well to compare the calculated and measured results. Good agreements are noticed between the calculated and measured results with maximum relative differences less than 7%, 4% and 4% in the x, y and z directions respectively. This agreement indicates that the established model is an accurate representation of the SGIF and can be used in the future to make the calculation design for a new irradiation facility.