Radiation safety evaluation of Bushehr Nuclear Power Plant Reactor Building in operation mode

In this study, radiation protection evaluations have been performed for Bushehr nuclear power plant (BNPP-1) reactor building. For this purpose, reactor building, shields and components were modeled using MCNPX code. Radiation source terms inside reactor building calculated at the end of first cycle using data obtained from the plant design documents and also coupling of MCNPX and ORIGEN codes. These data are applied in calculation of dose rates in reactor building simulation. Results of this evaluation are compared with the defined reactor building radiation zones presented in BNPP-1 FSAR documents. The comparisons show good agreement between calculated dose rates and dose limits presented in defined radiation zones in FSAR document.