A　new　pressure-vessel　type　supercritical　water　cooled　reactor　(SCWR)　core　concept　was　proposed　by　combining　merits　of　several　SCWR　core　designs　in　the　world.　This　core　design　employs　a　new　type　of　closed　assembly　with　double-row　fuel　rods　in　square　geometry　and　a　three-batch　low-leakage　refueling　scheme.　The　assembly　consists　of　two　rows　of　fuel　rods　and　a　moderator　rod,　which　causes　the　moderation　more　uniform.　The　three-batch　low　leakage　refueling　scheme　obviously　increases　the　cycle　length　and　reduces　the　neutron　fluence　on　the　pressure　vessel.　Three-dimensional　neutronics/thermohydraulics　coupling　calculation　shows　that　the　maximum　cladding　surface　temperature　(MCST)　is　684°C,　the　cycle　life　is　300　effective　full　power　days　and　the　power　distribution　is　flat.　Then　the　more　conservative　sub-channel　analysis　was　performed　for　all　fuel　assemblies.　The　MCST　was　evaluated　to　be　685.3°C,　showing　that　the　core　design　is　feasible.