openmc.DelayedGroupFilter

class openmc.DelayedGroupFilter(bins, filter_id=None)

Bins fission events based on the produced neutron precursor groups.

Parameters

• bins (iterable of int) – 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].

• filter_id (int) – Unique identifier for the filter

Variables

• bins (iterable of int) – 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].

• id (int) – Unique identifier for the filter

• num_bins (Integral) – The number of filter bins

check_bins(bins)

Make sure given bins are valid for this filter.

Raises

• TypeError –

• ValueError –