# openmc.Summary¶

class openmc.Summary(filename)[source]

Summary of geometry, materials, and tallies used in a simulation.

Variables: 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
add_volume_information(volume_calc)[source]

Add volume information to the geometry within the summary file

Parameters: volume_calc (openmc.VolumeCalculation) – Results from a stochastic volume calculation