JEFF-3.2 Processed Data: ACE continuous-energy cross section data

JEFF-3.2 neutron evaluations have been processed with the NJOY nuclear data processing system to generate ACE-formatted libraries suitable for Monte Carlo transport codes such as MCNP and SERPENT. Data are provided at multiple temperatures, from 293 K up to 1800 K, enabling accurate treatment of Doppler broadening effects in reactor physics and shielding simulations. These processed files support high-fidelity modelling of reactor cores, criticality benchmarks, and safety analyses where temperature-dependent cross sections are essential.