openmc.Geometry¶
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class
openmc.
Geometry
(root_universe=None)[source]¶ Geometry representing a collection of surfaces, cells, and universes.
Parameters: root_universe (openmc.Universe, optional) – Root universe which contains all others Variables: root_universe (openmc.Universe) – Root universe which contains all others -
find
(point)[source]¶ Find cells/universes/lattices which contain a given point
Parameters: point (3-tuple of float) – Cartesian coordinates of the point Returns: Sequence of universes, cells, and lattices which are traversed to find the given point Return type: list
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get_all_cells
()[source]¶ Return all cells defined
Returns: Cells in the geometry Return type: list of openmc.Cell
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get_all_lattices
()[source]¶ Return all lattices defined
Returns: Lattices in the geometry Return type: list of openmc.Lattice
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get_all_material_cells
()[source]¶ Return all cells filled by a material
Returns: Cells filled by Materials in the geometry Return type: list of openmc.Cell
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get_all_material_universes
()[source]¶ Return all universes composed of at least one non-fill cell
Returns: Universes with non-fill cells Return type: list of openmc.Universe
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get_all_materials
()[source]¶ Return all materials assigned to a cell
Returns: Materials in the geometry Return type: list of openmc.Material
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get_all_nuclides
()[source]¶ Return all nuclides assigned to a material in the geometry
Returns: Nuclides in the geometry Return type: list of openmc.Nuclide
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get_all_universes
()[source]¶ Return all universes defined
Returns: Universes in the geometry Return type: list of openmc.Universe
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get_cell_instance
(path)[source]¶ Return the instance number for the final cell in a geometry path.
The instance is an index into tally distribcell filter arrays.
Parameters: path (list) – A list of IDs that form the path to the target. It should begin with 0 for the base universe, and should cover every universe, cell, and lattice passed through. For the case of the lattice, a tuple should be provided to indicate which coordinates in the lattice should be entered. This should be in the form: (lat_id, i_x, i_y, i_z) Returns: instance – Index in tally results array for distribcell filters Return type: int
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get_cells_by_fill_name
(name, case_sensitive=False, matching=False)[source]¶ Return a list of cells with fills with matching names.
Parameters: Returns: Cells with fills matching the queried name
Return type: list of openmc.Cell
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get_cells_by_name
(name, case_sensitive=False, matching=False)[source]¶ Return a list of cells with matching names.
Parameters: Returns: Cells matching the queried name
Return type: list of openmc.Cell
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get_lattices_by_name
(name, case_sensitive=False, matching=False)[source]¶ Return a list of lattices with matching names.
Parameters: Returns: Lattices matching the queried name
Return type: list of openmc.Lattice
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get_materials_by_name
(name, case_sensitive=False, matching=False)[source]¶ Return a list of materials with matching names.
Parameters: Returns: Materials matching the queried name
Return type: list of openmc.Material
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