Abstract: A self-developed MCNP-ORIGEN coupled code MCORE was applied to perform neutronics and depletion calculations of the designed sodium cooled traveling wave reactor and standing wave reactor. Based on the power distribution obtained by MCORE, a self-developed sodium cooled fast reactor core steady state thermal-hydraulic analysis code SAST was applied to perform core thermal-hydraulic analysis of sodium cooled traveling wave reactor and standing wave reactor. The core physical and thermal hydraulic properties of sodium cooled traveling wave reactor and standing wave reactor were compared. The results show that standing wave reactor has advantages in burnup, maximum cladding and fuel temperatures, while traveling wave reactor has advantages in reactivity fluctuation and core outlet temperature uniformity.