Development of NECP-SARAX1.0 Code for Fast Reactor Physics Calculation

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 k_eff is around 100×10^-5.