Summary of geometry, materials, and tallies used in a simulation.
- date_and_time (str) – Date and time when simulation began
- geometry (openmc.Geometry) – The geometry reconstructed from the summary file
- materials (openmc.Materials) – The materials reconstructed from the summary file
- nuclides (dict) – Dictionary whose keys are nuclide names and values are atomic weight ratios.
- macroscopics (list) – Names of macroscopic data sets
- version (tuple of int) – Version of OpenMC