Abstract: The verification of thermal-hydraulic code is a focus of safety review. In order to verify the correctness of the analysis code through the comparison of different code calculation results, a detailed sub-channel calculation code SSCFR with independent intellectual property rights was developed for solid fuel core of sodium cooling fast reactor. Whole core steady analysis, sub-channel steady analysis and whole core transient analysis for China Experimental Fast Reactor (CEFR) were performed by using SSCFR. The results of SSCFR were compared with the operation and design values of CEFR, respectively. The results show that the calculation values of SSCFR agree well with the operation values and the calculation values of safety analysis report, and SSCFR can be used to the design of the Chinese Demonstration Fast Reactor (CDFR).