JEFF-3.1.2 Processed Data: ACE continuous-energy cross section data
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资源简介：
The JEFF-3.1.2 evaluated neutron files have been processed with the NJOY system to produce ACE-formatted data libraries for use in Monte Carlo transport codes such as MCNP and SERPENT. Cross sections are provided at a range of temperatures from 300 K up to 1800 K, enabling accurate modelling of Doppler broadening effects in criticality, shielding, and reactor physics calculations. These processed datasets support benchmark validation, reactor core simulations, and safety analyses requiring temperature-dependent nuclear data.
创建时间：
2025-10-15
