openmc.IndependentSource

class openmc.IndependentSource(space: Optional[Spatial] = None, angle: Optional[UnitSphere] = None, energy: Optional[Univariate] = None, time: Optional[Univariate] = None, strength: float = 1.0, particle: str = 'neutron', domains: Optional[Sequence[Union[Cell, Material, Universe]]] = None, constraints: Optional[Dict[str, Any]] = None)[source]

Distribution of phase space coordinates for source sites.

New in version 0.14.0.

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

  • strength (float) – Strength of the source

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

  • domains (iterable of openmc.Cell, openmc.Material, or openmc.Universe) –

    Domains to reject based on, i.e., if a sampled spatial location is not within one of these domains, it will be rejected.

    Deprecated since version 0.14.1: Use the constraints argument instead.

  • constraints (dict) – Constraints on sampled source particles. Valid keys include ‘domains’, ‘time_bounds’, ‘energy_bounds’, ‘fissionable’, and ‘rejection_strategy’. For ‘domains’, the corresponding value is an iterable of openmc.Cell, openmc.Material, or openmc.Universe for which sampled sites must be within. For ‘time_bounds’ and ‘energy_bounds’, the corresponding value is a sequence of floats giving the lower and upper bounds on time in [s] or energy in [eV] that the sampled particle must be within. For ‘fissionable’, the value is a bool indicating that only sites in fissionable material should be accepted. The ‘rejection_strategy’ indicates what should happen when a source particle is rejected: either ‘resample’ (pick a new particle) or ‘kill’ (accept and terminate).

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

  • time (openmc.stats.Univariate or None) – time distribution of source sites

  • strength (float) – Strength of the source

  • type (str) – Indicator of source type: ‘independent’

  • versionadded: (..) – 0.14.0:

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

  • constraints (dict) – Constraints on sampled source particles. Valid keys include ‘domain_type’, ‘domain_ids’, ‘time_bounds’, ‘energy_bounds’, ‘fissionable’, and ‘rejection_strategy’.

classmethod from_xml_element(elem: Element, meshes=None) → SourceBase[source]

Generate source from an XML element

Parameters

  • elem (lxml.etree._Element) – XML element

  • meshes (dict) – Dictionary with mesh IDs as keys and openmc.MeshBase instaces as values

Returns

Source generated from XML element

Return type

openmc.Source

populate_xml_element(element)[source]

Add necessary source information to an XML element

Returns

element – XML element containing source data

Return type

lxml.etree._Element