Processing and testing ENDF/B-VI with NJOY and TRANSX

摘要

The NJOY Nudear Data Processing System has been used to process the Evaluated Nuclear Data File ENDF/B-VI, including all changes through Release 2, into multigroup cross-section libraries that can be used with many different neutron/photon transport codes and into ACE format for use with the MCNP continuous-energy Monte Carlo code. The ENDF-6 format contains a number of new features of interest to reactor physics, and many of the new evaluations take advantage of these features to provided improved data. The changes to the NJOY system required to process these new evaluations are described. The new cross-section libraries have been used to test the performance of ENDF/B-VI for a number of familiar benchmarks. The results are compared to ENDF/B-V results to give an idea of how the new libraries will perform for reactor physics calculations.