JEFF-3.1.1 Processed Data: ACE continuous-energy cross section data

The JEFF-3.1.1 neutron evaluations have been processed with the NJOY system to produce ACE-formatted files for use in Monte Carlo transport codes such as MCNP and SERPENT. This dataset is available at a single temperature point of 300 K, supporting a broad range of benchmark, reactor physics, shielding, and criticality safety studies. These processed files provide a consistent link between the evaluated JEFF-3.1.1 library and practical applications requiring ACE-formatted nuclear data.