عنوان مقاله [English]
نویسندگان [English]چکیده [English]
In this research, required information to simulate and perform neutronic calculations for Bushehr nuclear power plant using the MCNPX code was provided. The results of the code were verified with at least one of the operational data from the reactor. In this work, by writing and implementing a comprehensive program to solve the equations of statistical distribution, neutron flux was obtained and then various parameters including the infinite multiplication factor in terms of fluence were calculated and the control rod worth for Groups 9 and 10 were calculated at Hot Zero Power (HZP) state.