openmc.deplete.AtomNumber¶
- class openmc.deplete.AtomNumber(local_mats, nuclides, volume, n_nuc_burn)[source]¶
Stores local material compositions (atoms of each nuclide).
- Parameters
- Variables
index_mat (dict) – A dictionary mapping material ID as string to index.
index_nuc (dict) – A dictionary mapping nuclide name to index.
volume (numpy.ndarray) – Volume of each material in [cm^3]. If a volume is not found, it defaults to 1 so that reading density still works correctly.
number (numpy.ndarray) – Array storing total atoms for each material/nuclide
materials (list of str) – Material IDs as strings
nuclides (list of str) – All nuclide names
burnable_nuclides (list of str) – Burnable nuclides names. Used for sorting the simulation.
n_nuc_burn (int) – Number of burnable nuclides.
n_nuc (int) – Number of nuclides.
- get_mat_slice(mat)[source]¶
Gets atom quantity indexed by mats for all burned nuclides
- Parameters
- Returns
The slice requested in [atom].
- Return type