Abstract: A coupled neutronics and thermal-hydraulics code was developed for the graphite-moderated channel-type molten salt reactor. Analytic basis functions expansion nodal method in triangular geometry and multiple-channel model were employed for the reactor physics calculation and thermal-hydraulics calculation respectively. For the molten salt reactor experiment (MSRE), the results from the ORNL technical report were used for code validation. In addition, the 3D power distribution, mass flow distribution, temperature of molten salt and graphite were calculated at steady state.