Abstract
A new nuclear data processing code called NECP-Atlas is under development at Xi’an Jiaotong University in China. The motivation for the development is to establish a platform to carry out deeper researches on nuclear data processing methods to satisfy the demands on accurate cross sections in the fields of high-fidelity transport simulation and advanced reactor design. The present paper describes the methods used in the current version of NECP-Atlas and demonstrates the performance and accuracy of the code on a variety of benchmarks. At the present time, NECP-Atlas can process ENDF/B-VII.1, ENDF/B-VII.0, CENDL-3.1, JEFF-3.2 and JENDL-4.0 evaluations, and generate WIMS-D and ACE format libraries. The accuracy of the code is comparable with NJOY2016. NECP-Atlas is competent to provide cross sections for deterministic and Monte Carlo transport calculations.
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