openmc.CellFromFilter¶
-
class
openmc.
CellFromFilter
(bins, filter_id=None)[source]¶ Bins tally on which Cell the neutron came from.
Parameters: - bins (openmc.Cell, Integral, or iterable thereof) – The Cell(s) to tally. Either openmc.Cell objects or their Integral ID numbers can be used.
- filter_id (int) – Unique identifier for the filter
Variables: -
expected_type
¶ alias of
openmc.cell.Cell