openmc.EnergyFilter¶

class openmc.EnergyFilter(values, filter_id=None)[source]¶

Bins tally events based on incident particle energy.

Parameters:	values (Iterable of Real) – A list of values for which each successive pair constitutes a range of energies in [eV] for a single bin filter_id (int) – Unique identifier for the filter
Variables:	values (numpy.ndarray) – An array of values for which each successive pair constitutes a range of energies in [eV] for a single bin id (int) – Unique identifier for the filter bins (numpy.ndarray) – An array of shape (N, 2) where each row is a pair of energies in [eV] for a single filter bin num_bins (int) – The number of filter bins

check_bins(bins)[source]¶

Make sure given bins are valid for this filter.

Raises:	`TypeError` `ValueError`

get_bin_index(filter_bin)[source]¶

Returns the index in the Filter for some bin.

Parameters:	filter_bin (int or tuple) – The bin is the integer ID for ‘material’, ‘surface’, ‘cell’, ‘cellborn’, and ‘universe’ Filters. The bin is an integer for the cell instance ID for ‘distribcell’ Filters. The bin is a 2-tuple of floats for ‘energy’ and ‘energyout’ filters corresponding to the energy boundaries of the bin of interest. The bin is an (x,y,z) 3-tuple for ‘mesh’ filters corresponding to the mesh cell of interest.
Returns:	filter_index – The index in the Tally data array for this filter bin.
Return type:	int