The SARAX (System for Advance Reactor Analysis at Xi’an Jiaotong University) code system aims to model and simulate the neutronics behaviors of reactors and subcritical facilities with fast spectrum, which consists of 4 parts including TULIP for cross-section generation, LAVENDER for steady state core analysis, DAISY for transient analysis and COLEUS for S&U analysis. The code system is capable of doing the neutronics analysis for SFR, LFR and LBE cooled ADS reactors. Verifications and validations based on over 100 numerical benchmarks and physical experiments have been done to prove its accuracy and capabilities.
Basic functions and features
   ◆ Core analysis based on three-dimensional neutron transport calculation
        - Arbitrary-order SN transport calculation
        - Up to P3 anisotropic scattering in the core calculation
        - Perturbation theory and Virtual density method for the reactivity evaluation
   ◆ Transient analysis based on point kinetics and spatial dependent kinetics method
        - Spatially dependent reactivity feedback for the point kinetics
        - Prediction-correction quasi-steady method based on the neutron transport calculation
        - Integrated T-H feedback for sodium, lead and LBE
   ◆ Sensitivity and uncertainty analysis
        - Uncertainty quantification of keff, power distribution and reactivity effect
        - Similarity analysis for the experiment assessment
        - Nuclear data adjustment for the multi-group and ACE libraries