openmc.Source

class openmc.Source(space=None, angle=None, energy=None, filename=None, library=None, strength=1.0, particle='neutron')

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

  Path to a custom source library

  New in version 0.12.

• strength (float) – Strength of the source
• particle ({'neutron', 'photon'}) – Source particle type

Variables:

• space (openmc.stats.Spatial or None) – Spatial distribution of source sites
• angle (openmc.stats.UnitSphere or None) – Angular distribution of source sites
• energy (openmc.stats.Univariate or None) – Energy distribution of source sites
• file (str or None) – Source file from which sites should be sampled
• library (str or None) – Path to a custom source library
• strength (float) – Strength of the source
• particle ({'neutron', 'photon'}) – Source particle type

classmethod from_xml_element(elem)

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()

Return XML representation of the source

Returns:element – XML element containing source data Return type:xml.etree.ElementTree.Element