openmc.Source

class openmc.Source(space=None, angle=None, energy=None, time=None, filename=None, library=None, parameters=None, strength=1.0, particle='neutron')[source]

Distribution of phase space coordinates for source sites.

Parameters
  • space (openmc.stats.Spatial) – Spatial distribution of source sites

  • angle (openmc.stats.UnitSphere) – Angular distribution of source sites

  • energy (openmc.stats.Univariate) – Energy distribution of source sites

  • time (openmc.stats.Univariate) – time distribution of source sites

  • filename (str) – Source file from which sites should be sampled

  • library (str) – Path to a custom source library

  • parameters (str) –

    Parameters to be provided to the custom source library

    New in version 0.12.

  • strength (float) – Strength of the source

  • particle ({'neutron', 'photon'}) – Source particle type

Variables
classmethod from_xml_element(elem)[source]

Generate source from an XML element

Parameters

elem (xml.etree.ElementTree.Element) – XML element

Returns

Source generated from XML element

Return type

openmc.Source

to_xml_element()[source]

Return XML representation of the source

Returns

element – XML element containing source data

Return type

xml.etree.ElementTree.Element