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　For　further　design　analysis,　parametric　studies　are　performed　to　provide　valuable　information　for　new　design　of　MSR.　The　effect　of　inlet　temperature,　graphite　to　molten　salt　volume　ratio　(G/Ms)　from　varying　channel　diameter　and　different　power　levels　on　the　effective　multiplication　factor,　neutron　flux,　graphite　lifetime　and　temperature　distribution　are　discussed　in　detail.　(C)　2013　Elsevier　B.V.　All　rights　reserved.