Neutronic analysis on TRU multi-recycling in PWR-based SMR core loaded with MOX (U-TRU) and FCM (TRU) fueled assemblies

Abstract

An analysis on TRU multi-recycling in a light water-cooled SMR core loaded with MOX-FCM fuel assemblies employing MOX and FCM (Fully Ceramic Micro-encapsulated) fuel rods was performed for TRU transmutation. We used a two-step procedure composed of McCARD/MASTER where the assembly-wise two group homogenized neutron cross sections are generated using a Monte Carlo depletion code, while the core analysis was performed using a two-group nodal diffusion code. The reload core calculation based on three-batch refueling scheme was conducted using a TRU recycling scheme in which TRU in MOX fuel rods are multi-recycled but TRUs in FCM fuel ones are sent to the final repository after the discharge without recycling. An overall TRU mass balance analysis through the 5th to 20th cycle showed that 21.1% of external TRU feed can be consumed by utilizing the light water-cooled SMR core without considerable degradation of safety-related parameters.