Abstract: Aiming at developing system analysis code independently, a system analysis code for pool-type fast reactor in China (SAC-CFR), with neutron kinetics model, core and hot pool model, intermediate heat exchanger model, primary and intermediate heat transport system, steam generation system, was developed based on Compaq Visual Fortran (CVF) to analyze the thermal-hydraulic characteristic of fast reactor under steady state operation. The simulation results of China Experimental Fast Reactor (CEFR) with SAC-CFR were compared with those in CEFR safety analysis report. The good agreements between them show that the present model is effective, which makes preparations for further development of transient model and plant protection and plant control system.