openmc.Source¶
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class
openmc.
Source
(space=None, angle=None, energy=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
- 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: - 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
- parameters (str) – Parameters to be provided to the custom source library
- strength (float) – Strength of the source
- particle ({'neutron', 'photon'}) – Source particle type
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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
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to_xml_element
()[source]¶ Return XML representation of the source
Returns: element – XML element containing source data Return type: xml.etree.ElementTree.Element