openmc.Cell¶

class
openmc.
Cell
(cell_id=None, name='', fill=None, region=None)[source]¶ A region of space defined as the intersection of halfspace created by quadric surfaces.
Parameters:  cell_id (int, optional) – Unique identifier for the cell. If not specified, an identifier will automatically be assigned.
 name (str, optional) – Name of the cell. If not specified, the name is the empty string.
 fill (openmc.Material or openmc.Universe or openmc.Lattice or None or iterable of openmc.Material, optional) – Indicates what the region of space is filled with
 region (openmc.Region, optional) – Region of space that is assigned to the cell.
Variables:  id (int) – Unique identifier for the cell
 name (str) – Name of the cell
 fill (openmc.Material or openmc.Universe or openmc.Lattice or None or iterable of openmc.Material) – Indicates what the region of space is filled with. If None, the cell is treated as a void. An iterable of materials is used to fill repeated instances of a cell with different materials.
 fill_type ({'material', 'universe', 'lattice', 'distribmat', 'void'}) – Indicates what the cell is filled with.
 region (openmc.Region or None) – Region of space that is assigned to the cell.
 rotation (Iterable of float) –
If the cell is filled with a universe, this array specifies the angles in degrees about the x, y, and z axes that the filled universe should be rotated. The rotation applied is an intrinsic rotation with specified TaitBryan angles. That is to say, if the angles are \((\phi, \theta, \psi)\), then the rotation matrix applied is \(R_z(\psi) R_y(\theta) R_x(\phi)\) or
\[\left [ \begin{array}{ccc} \cos\theta \cos\psi & \cos\phi \sin\psi + \sin\phi \sin\theta \cos\psi & \sin\phi \sin\psi + \cos\phi \sin\theta \cos\psi \\ \cos\theta \sin\psi & \cos\phi \cos\psi + \sin\phi \sin\theta \sin\psi & \sin\phi \cos\psi + \cos\phi \sin\theta \sin\psi \\ \sin\theta & \sin\phi \cos\theta & \cos\phi \cos\theta \end{array} \right ]\]  rotation_matrix (numpy.ndarray) – The rotation matrix defined by the angles specified in the
Cell.rotation
property.  temperature (float or iterable of float) – Temperature of the cell in Kelvin. Multiple temperatures can be given to give each distributed cell instance a unique temperature.
 translation (Iterable of float) – If the cell is filled with a universe, this array specifies a vector that is used to translate (shift) the universe.
 paths (list of str) – The paths traversed through the CSG tree to reach each cell
instance. This property is initialized by calling the
Geometry.determine_paths()
method.  num_instances (int) – The number of instances of this cell throughout the geometry.
 volume (float) – Volume of the cell in cm^3. This can either be set manually or
calculated in a stochastic volume calculation and added via the
Cell.add_volume_information()
method.

add_volume_information
(volume_calc)[source]¶ Add volume information to a cell.
Parameters: volume_calc (openmc.VolumeCalculation) – Results from a stochastic volume calculation

clone
(memo=None)[source]¶ Create a copy of this cell with a new unique ID, and clones the cell’s region and fill.
Parameters: memo (dict or None) – A nested dictionary of previously cloned objects. This parameter is used internally and should not be specified by the user. Returns: clone – The clone of this cell Return type: openmc.Cell

classmethod
from_xml_element
(elem, surfaces, materials, get_universe)[source]¶ Generate cell from XML element
Parameters:  elem (xml.etree.ElementTree.Element) – <cell> element
 surfaces (dict) – Dictionary mapping surface IDs to
openmc.Surface
instances  materials (dict) – Dictionary mapping material IDs to
openmc.Material
instances (defined in \(openmc.Geometry.from_xml\))  get_universe (function) – Function returning universe (defined in
openmc.Geometry.from_xml()
)
Returns: Cell instance
Return type:

get_all_cells
()[source]¶ Return all cells that are contained within this one if it is filled with a universe or lattice
Returns: cells – Dictionary whose keys are cell IDs and values are Cell
instancesReturn type: collections.orderedDict

get_all_materials
()[source]¶ Return all materials that are contained within the cell
Returns: materials – Dictionary whose keys are material IDs and values are Material
instancesReturn type: collections.OrderedDict

get_all_universes
()[source]¶ Return all universes that are contained within this one if any of its cells are filled with a universe or lattice.
Returns: universes – Dictionary whose keys are universe IDs and values are Universe
instancesReturn type: collections.OrderedDict

get_nuclide_densities
()[source]¶ Return all nuclides contained in the cell and their densities
Returns: nuclides – Dictionary whose keys are nuclide names and values are 2tuples of (nuclide, density) Return type: collections.OrderedDict