Abstract: Lead-bismuth/lead cooled fast reactor (LFR) is one of the fourth-generation advanced nuclear energy systems with good application prospects. Aiming at the application of two metallic fuels (UZr, UPuZr) with annular slug in an LFR fuel assembly and a typical LFR core, the Dragon/Donjon code was used to perform neutronics calculations. The results of 172-group and 295-group neutron databases based on the ENDF/B 8.0 library and the transport method (SP3) and the diffusion method (MCFD) were obtained and compared with the results using RMC code. The k_eff deviations using SP3 algorithm for UZr fuel are less than 550×10⁻⁵, and for UPuZr fuel, the k_eff deviations obtained by MCFD algorithm are less than −700×10⁻⁵. The maximum deviation of control rod worth is 7.6%, and the results using 172-grouplib and 295-grouplib are basically the same. By using the SP3 algorithm, the fuel assembly power deviations are less than ±6.0%, and the deviation with the SP3 algorithm is less than that with MCFD algorithm. The results preliminarily prove the feasibility of the Dragon/Donjon code for reactor physics analysis of LFR with metallic fuel.