Abstract: Due to the complexity of flow and heat transfer behavior of lead bismuth eutectic (LBE) coolant, it is important to calculate the coolant and cladding temperature of wire-wrapped fuel assembly cooled by LBE accurately. In this study, the conservation equations were solved by lump parameter method. A subchannel analysis code was developed for lead-bismuth cooled fast reactor, and the applicability of the friction resistance model, turbulent mixing model and heat transfer model of LBE was analyzed. The results with the large eddy simulation data of 7 pins bundle and the heat transfer experiment of 19 pins bundle were compared. The results show that the maximum relative errors of cladding and coolant temperatures are both less than 5%. It is proved that the code is able to accomplish the thermal hydraulic calculation of LBE cooled wire-wrapped fuel assembly, which can provide support for the design of lead-bismuth cooled fast reactor.