JEFF-4.0 Processed Data: ACE continuous-energy cross section data
收藏DataCite Commons2025-06-19 更新2026-05-03 收录
下载链接：
https://data.oecd-nea.org/doi/10.82555/53ret-j3386
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资源简介：
Processed data associated to JEFF-4.0 nuclear data library: ACE-format continuous-energy cross section data at 293.6, 300, 600, 900, 1200, 1500 and 1800 K.
This dataset contains continuous-energy neutron cross section files in ACE format, processed from the JEFF-4.0 593 target nuclear data library using NJOY2016.78. Cross sections were generated at seven temperatures: 293.6 K, 300 K, 600 K, 900 K, 1200 K, 1500 K, and 1800 K. These files are suitable for Monte Carlo neutron transport simulations. A separate thermal scattering law file is available and not included in this record. The processing ensures compatibility with codes such as MCNP and OpenMC, facilitating high-fidelity reactor physics, shielding, and criticality safety analyses.
提供机构：
OECD Nuclear Energy Agency
创建时间：
2025-06-19
