JEFF-3.2 Processed Data: ACE continuous-energy cross section data
收藏DataCite Commons2025-10-17 更新2026-05-03 收录
下载链接：
https://data.oecd-nea.org/doi/10.82555/dg3wa-7p407
下载链接
链接失效反馈官方服务：
资源简介：
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.
提供机构：
OECD Nuclear Energy Agency
创建时间：
2025-10-17
