ENDF/B-VII Thermal Data |
Warning: the ACE files available from this page are for an experimental continuous thermal scattering treatment that helps to prevent artifacts in the flux coming from the discrete energies used in the standard MCNP thermal treatment. This treatment is not available in standard versions of MCNP, although some versions of MCNPX do support it. Using these files in MCNP can lead to serious errors in your results. |
Custom 2D and 3D plots of the thermal scattering data can be made using the Nuclear Data Viewer. Select the data type ENDFB-VII-thermal, and look for the thermal cross sections or distributions (MT221, 222, etc.) |