A　new　code　NECP-SARAX1.0　is　developed　for　the　nuclear　design　and　steady　analysis　of　the　fast　reactor　core　based　on　the　special　features　of　fast　reactor　physics.　The　continuous　energy　cross　section　library　from　ENDF/BVII　is　used.　The　OPENMC　code　is　adopted　to　generate　the　multi-group　cross　sections.　The　SN-nodal　method　transport　is　applied　in　the　core　calculation　based　on　the　unstructured　mesh　modeling.　It　is　suitable　for　both　the　critical　and　subcritical　core　calculation.　The　perturbation　method　is　used　to　calculate　the　Doppler　coefficients.　Numerical　results　show　that　the　new　code　is　of　high　precision.　Compared　with　direct　MCNP　calculation,　the　difference　of　keffis　around　100×10-5.　©,　2014,　Yuan　Zi　Neng　Chuban　She.　All　right　reserved.