openmc.DelayedGroupFilter¶
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class
openmc.DelayedGroupFilter(bins)[source]¶ Bins fission events based on the produced neutron precursor groups.
Parameters: bins (Integral or Iterable of Integral) – The delayed neutron precursor groups. For example, ENDF/B-VII.1 uses 6 precursor groups so a tally with all groups will have bins = [1, 2, 3, 4, 5, 6].
Variables: - bins (Integral or Iterable of Integral) – The delayed neutron precursor groups. For example, ENDF/B-VII.1 uses 6 precursor groups so a tally with all groups will have bins = [1, 2, 3, 4, 5, 6].
- num_bins (Integral) – The number of filter bins
- stride (Integral) – The number of filter, nuclide and score bins within each of this filter’s bins.