Molten corium-concrete interaction is an important phenomenon in the late phase of severe accident, threatening the integrity of containment and might causing potential large release of radioactivity. Even though a reactor adopts in-vessel retention strategy, MCCI analysis is still important in the support of the level-2 probabilistic safety assessment (PSA). To simulate the MCCI process, a MCCI dedicated simulation code was developed. The govern equations are established based on lumped parametric modelling, including both axial and radial heat transfer from molten pool to concrete, thermal-chemical reactions in the corium, crust growth and remelt, and coolability mechanisms. This code can predict the 2-D corium erosion and gas release from the corium, which are important for the reactor case. Representative MCCI experiment tests simulated by applying this code to verify the models. The results were also compared with other mainstream MCCI analysis code such as ASTEC (MEDICIS) (Cranga et al. in Proceedings of ICAPP05, Seoul, Korea (2005) ). The verification results show good agreements. An application practice was also performed in the simulation of a 1000 MW third-generation reactor scenario.