Radiation Shielding Analysis for the Reactor Assembly of the SMART Reactor

Abstract

A 660 MWt integral reactor SMART (System integrated Modular Advanced ReacTor), called SMART-660, is under development in Korea as a national research and development project to supply energy for a seawater desalination as well as an electricity generation. A radiation shielding analysis has been carried out to evaluate the shielding design of the SMART-660. Two-dimensional discrete ordinates transport code DORT was used to calculate the neutron and gamma dose rates and the fast neutron fluences in the reactor pressure vessel assembly (RPV). The reactor assembly of the SMART-660 was modeled as an R-Z geometry through an azimuthal homogenization of the reactor components. The GEOSHIELD program was used to generate the DORT input file and process the DORT output file with a graphic visualization. The neutron 47-group and gamma 20-group BUGLE-96 cross-section library was used for the DORT calculation. It is found that the integrity of the RPV is preserved throughout the reactor lifetime and the shielding system of the SMART-660 is satisfactory to prevent radiation escaping from the reactor core.