JEFF-3.1.1 Processed Data: ACE continuous-energy cross section data
收藏DataCite Commons2025-10-21 更新2026-05-03 收录
下载链接：
https://data.oecd-nea.org/doi/10.82555/vm6q9-z8j63
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资源简介：
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.
提供机构：
OECD Nuclear Energy Agency
创建时间：
2025-10-21
