Development and verification of a new nuclear data processing code AXSP

The advanced reactor design needs an accurate cross-section generation code. In this study, a new nuclear data processing code AXSP is developed, and the method performance of which are described. Compared with NJOY program, precision unresolved resonance module UnresXS has been significantly improved due to adoption more solution consideration in-sequence overlap integrals. time consumption PUnresXS decreased optimized sorting algorithm. At same time, other modules relatively comprehensive. function resolved reconstruction linearization ReconXS module. Doppler broadening BroadXS by using Gauss–Hermite quadrature Gauss–Legendre from 0 K temperature pointwise cross section any defined user. shielding factor in energy region calculated or module, developed based on Bondarenko probability table method, respectively. ACE formatted sections for Monte Carlo processed ACEXS multigroup generated GroupXS different were verified NJOY2016 code, also critical benchmarks. multiplication difference between less than 20 pcm. addition this, ZPR6/7 fast used format library verification. results show that criticality good agreement NJOY2016.