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
  • bins (Integral or Iterable of Integral) – openmc.Cell IDs.

  • id (int) – Unique identifier for the filter

  • num_bins (Integral) – The number of filter bins

expected_type

alias of openmc.cell.Cell