Gamma and neutron dose assessment for the spent fuel storage pool of a VVER-1000 reactor using an updated cross-section library under steady-state conditions

Abstract Spent fuel storage pools in nuclear power plants are designed to safely contain spent fuel assemblies, minimizing radioactive emissions and radiation exposure to both personnel and the environment. After irradiation in the reactor core, spent fuel assemblies, due to their residual radioactivity, are transferred to these pools to prevent environmental contamination. This study aims to quantify the gamma and neutron radiation doses emitted from the spent fuel storage pool and its surrounding areas using an updated nuclear cross-section library. To achieve this, a VVER-1000 reactor was modeled using the MCNPX code to generate a cross-section library for the ORIGEN2 code. Subsequently, the radiation dose in the spent fuel storage pool was calculated under maximum accumulation conditions at steady state. The results demonstrate a significant radiation dose around the pool and highlight the substantial role of the power plant building in reducing radiation levels.