Abstract: According to the characteristics of structure and steady-state for primary loop of China Experimental Fast Reactor (CEFR), a thermal-hydraulic steady-state analysis program was developed by using Fortran language. This paper focused on the development of a set of subroutine of physical properties of sodium and the sodium flow and heat transfer correlations for different operation conditions. And the difference among these correlations was compared. The calculation program was developed based on the steady model. At last, the thermal-hydraulic characteristics of steady-state of the primary loop of CEFR at full power were calculated. The calculation results are consistent with the design parameters and the correctness of the developed subroutines and steady-state calculation program was proved.