Abstract: For the supercritical water-cooled reactor (SCWR), a supercritical core fuel management code Xpack which was based on nodal method was developed. The code included a neutronic calculation module, a thermal-hydraulic calculation module and a program flow construction module. It could achieve the coupling of neutronic and thermal hydraulic calculation in the whole burnup steps. The calculation results of Xpack and SRAC2K6/SPROD codes were campared. The results show that the calculated results of Xpack are in good agreement with those of SRAC2K6/SPROD code, and the computational efficiency of Xpack increases about 60 times. The Xpack code is efficient and reliable.