2. Notes on database

2.1. How to obtain the database

RMC utilizes ACE format neutron cross section libraries (same as MCNP, OpenMC, etc.), which are processed from evaluated nuclear databases (e.g., ENDF/B) using nuclear data processing codes such as NJOY and RXSP.

Typically, the basic neutron cross section libraries are provided in the RMC package, which are processed from ENDF/B-VII.1 using NJOY. If you have further needs, please contact us (contact@reallab.org.cn and https://forum.reallab.org.cn).

You can also view or download nuclear data from the National Nuclear Data Center, such as 293.6K neutron cross section library, 300K neutron cross section library, thermal neutron scattering cross section library, which are all based on ENDF/B-VII.1 (all with xsdir index file).