The　Generation　IV　international　Forum　(GIF)　selected　molten　salt　reactor　(MSR)　among　six　advanced　reactor　types.　It　is　characterized　by　a　liquid　circulating　fuel　that　also　serves　as　coolant.　In　this　study,　a　multiple-channel　analysis　code　(MAC)　is　developed　and　it　is　coupled　with　MCNP4c　to　analyze　the　neutronics/thermal-hydraulics　behavior　of　Molten　Salt　Reactor　Experiment　(MSRE).　The　MAC　calculates　thermal-hydraulic　parameters,　such　as　temperature　distribution,　flow　distribution　and　pressure　drop.　MCNP4c　performs　the　analysis　of　effective　multiplication　factor,　neutron　flux　and　power　distribution.　A　linkage　code　is　developed　to　exchange　data　between　MAC　and　MCNP　to　implement　coupling　iteration　process　until　the　power　convergence　is　achieved.　The　coupling　calculation　can　achieve　converged　solution　after　a　few　iterations.　The　results　are　in　reasonable　agreement　with　the　analytic　solutions　from　the　ORNL.　This　work　was　helpful　for　further　design　analysis　and　operation　of　MSR.