from collections.abc import Iterable
from math import cos, sin, pi
from numbers import Real
import lxml.etree as ET
import numpy as np
from uncertainties import UFloat
import openmc
import openmc.checkvalue as cv
from ._xml import get_text
from .mixin import IDManagerMixin
from .plots import add_plot_params
from .region import Region, Complement
from .surface import Halfspace
from .bounding_box import BoundingBox
[docs]class Cell(IDManagerMixin):
r"""A region of space defined as the intersection of half-space 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.UniverseBase 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.
Attributes
----------
id : int
Unique identifier for the cell
name : str
Name of the cell
fill : openmc.Material or openmc.UniverseBase 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
Tait-Bryan angles. That is to say, if the angles are :math:`(\phi,
\theta, \psi)`, then the rotation matrix applied is :math:`R_z(\psi)
R_y(\theta) R_x(\phi)` or
.. math::
\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 ]
A rotation matrix can also be specified directly by setting this
attribute to a nested list (or 2D numpy array) that specifies each
element of the matrix.
rotation_matrix : numpy.ndarray
The rotation matrix defined by the angles specified in the
:attr:`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
:meth:`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
:meth:`Cell.add_volume_information` method. For 'distribmat' cells
it is the total volume of all instances.
atoms : dict
Mapping of nuclides to the total number of atoms for each nuclide
present in the cell, or in all of its instances for a 'distribmat'
fill. For example, {'U235': 1.0e22, 'U238': 5.0e22, ...}.
.. versionadded:: 0.12
bounding_box : openmc.BoundingBox
Axis-aligned bounding box of the cell
"""
next_id = 1
used_ids = set()
def __init__(self, cell_id=None, name='', fill=None, region=None):
# Initialize Cell class attributes
self.id = cell_id
self.name = name
self.fill = fill
self.region = region
self._rotation = None
self._rotation_matrix = None
self._temperature = None
self._translation = None
self._paths = None
self._num_instances = None
self._volume = None
self._atoms = None
def __contains__(self, point):
if self.region is None:
return True
else:
return point in self.region
def __repr__(self):
string = 'Cell\n'
string += '{: <16}=\t{}\n'.format('\tID', self.id)
string += '{: <16}=\t{}\n'.format('\tName', self.name)
if self.fill_type == 'material':
string += '{: <16}=\tMaterial {}\n'.format('\tFill', self.fill.id)
elif self.fill_type == 'void':
string += '{: <16}=\tNone\n'.format('\tFill')
elif self.fill_type == 'distribmat':
string += '{: <16}=\t{}\n'.format('\tFill', list(map(
lambda m: m if m is None else m.id, self.fill)))
else:
string += '{: <16}=\t{}\n'.format('\tFill', self.fill.id)
string += '{: <16}=\t{}\n'.format('\tRegion', self.region)
string += '{: <16}=\t{}\n'.format('\tRotation', self.rotation)
if self.fill_type == 'material':
string += '\t{0: <15}=\t{1}\n'.format('Temperature',
self.temperature)
string += '{: <16}=\t{}\n'.format('\tTranslation', self.translation)
string += '{: <16}=\t{}\n'.format('\tVolume', self.volume)
return string
@property
def name(self):
return self._name
@name.setter
def name(self, name):
if name is not None:
cv.check_type('cell name', name, str)
self._name = name
else:
self._name = ''
@property
def fill(self):
return self._fill
@fill.setter
def fill(self, fill):
if fill is not None:
if isinstance(fill, Iterable):
for i, f in enumerate(fill):
if f is not None:
cv.check_type('cell.fill[i]', f, openmc.Material)
elif not isinstance(fill, (openmc.Material, openmc.Lattice,
openmc.UniverseBase)):
msg = (f'Unable to set Cell ID="{self._id}" to use a '
f'non-Material or Universe fill "{fill}"')
raise ValueError(msg)
self._fill = fill
# Info about atom content can now be invalid
# (since fill has just changed)
self._atoms = None
@property
def fill_type(self):
if isinstance(self.fill, openmc.Material):
return 'material'
elif isinstance(self.fill, openmc.UniverseBase):
return 'universe'
elif isinstance(self.fill, openmc.Lattice):
return 'lattice'
elif isinstance(self.fill, Iterable):
return 'distribmat'
else:
return 'void'
@property
def region(self):
return self._region
@region.setter
def region(self, region):
if region is not None:
cv.check_type('cell region', region, Region)
self._region = region
@property
def rotation(self):
return self._rotation
@rotation.setter
def rotation(self, rotation):
cv.check_length('cell rotation', rotation, 3)
self._rotation = np.asarray(rotation)
# Save rotation matrix -- the reason we do this instead of having it be
# automatically calculated when the rotation_matrix property is accessed
# is so that plotting on a rotated geometry can be done faster.
if self._rotation.ndim == 2:
# User specified rotation matrix directly
self._rotation_matrix = self._rotation
else:
phi, theta, psi = self.rotation*(-pi/180.)
c3, s3 = cos(phi), sin(phi)
c2, s2 = cos(theta), sin(theta)
c1, s1 = cos(psi), sin(psi)
self._rotation_matrix = np.array([
[c1*c2, c1*s2*s3 - c3*s1, s1*s3 + c1*c3*s2],
[c2*s1, c1*c3 + s1*s2*s3, c3*s1*s2 - c1*s3],
[-s2, c2*s3, c2*c3]])
@property
def rotation_matrix(self):
return self._rotation_matrix
@property
def temperature(self):
return self._temperature
@temperature.setter
def temperature(self, temperature):
# Make sure temperatures are positive
cv.check_type('cell temperature', temperature, (Iterable, Real), none_ok=True)
if isinstance(temperature, Iterable):
cv.check_type('cell temperature', temperature, Iterable, Real)
for T in temperature:
cv.check_greater_than('cell temperature', T, 0.0, True)
elif isinstance(temperature, Real):
cv.check_greater_than('cell temperature', temperature, 0.0, True)
# If this cell is filled with a universe or lattice, propagate
# temperatures to all cells contained. Otherwise, simply assign it.
if self.fill_type in ('universe', 'lattice'):
for c in self.get_all_cells().values():
if c.fill_type == 'material':
c._temperature = temperature
else:
self._temperature = temperature
@property
def translation(self):
return self._translation
@translation.setter
def translation(self, translation):
cv.check_type('cell translation', translation, Iterable, Real)
cv.check_length('cell translation', translation, 3)
self._translation = np.asarray(translation)
@property
def volume(self):
return self._volume
@volume.setter
def volume(self, volume):
if volume is not None:
cv.check_type('cell volume', volume, (Real, UFloat))
cv.check_greater_than('cell volume', volume, 0.0, equality=True)
self._volume = volume
# Info about atom content can now be invalid
# (since volume has just changed)
self._atoms = None
@property
def atoms(self):
if self._atoms is None:
if self._volume is None:
msg = ('Cannot calculate atom content because no volume '
'is set. Use Cell.volume to provide it or perform '
'a stochastic volume calculation.')
raise ValueError(msg)
elif self.fill_type == 'void':
msg = ('Cell is filled with void. It contains no atoms. '
'Material must be set to calculate atom content.')
raise ValueError(msg)
elif self.fill_type in ['lattice', 'universe']:
msg = ('Universe and Lattice cells can contain multiple '
'materials in diffrent proportions. Atom content must '
'be calculated with stochastic volume calculation.')
raise ValueError(msg)
elif self.fill_type == 'material':
# Get atomic densities
self._atoms = self._fill.get_nuclide_atom_densities()
# Convert to total number of atoms
for key, atom_per_bcm in self._atoms.items():
atom = atom_per_bcm * self._volume * 1.0e+24
self._atoms[key] = atom
elif self.fill_type == 'distribmat':
# Assumes that volume is total volume of all instances
# Also assumes that all instances have the same volume
partial_volume = self.volume / len(self.fill)
self._atoms = {}
for mat in self.fill:
for key, atom_per_bcm in mat.get_nuclide_atom_densities().items():
# To account for overlap of nuclides between distribmat
# we need to append new atoms to any existing value
# hence it is necessary to ask for default.
atom = self._atoms.setdefault(key, 0)
atom += atom_per_bcm * partial_volume * 1.0e+24
self._atoms[key] = atom
else:
msg = f'Unrecognized fill_type: {self.fill_type}'
raise ValueError(msg)
return self._atoms
@property
def paths(self):
if self._paths is None:
raise ValueError('Cell instance paths have not been determined. '
'Call the Geometry.determine_paths() method.')
return self._paths
@property
def bounding_box(self):
if self.region is not None:
return self.region.bounding_box
else:
return BoundingBox.infinite()
@property
def num_instances(self):
if self._num_instances is None:
raise ValueError(
'Number of cell instances have not been determined. Call the '
'Geometry.determine_paths() method.')
return self._num_instances
[docs] def get_nuclides(self):
"""Returns all nuclides in the cell
Returns
-------
nuclides : list of str
List of nuclide names
"""
return self.fill.get_nuclides() if self.fill_type != 'void' else []
[docs] def get_nuclide_densities(self):
"""Return all nuclides contained in the cell and their densities
Returns
-------
nuclides : dict
Dictionary whose keys are nuclide names and values are 2-tuples of
(nuclide, density)
"""
nuclides = {}
if self.fill_type == 'material':
nuclides.update(self.fill.get_nuclide_densities())
elif self.fill_type == 'void':
pass
else:
if self._atoms is not None:
volume = self.volume
for name, atoms in self._atoms.items():
density = 1.0e-24 * atoms.n/volume # density in atoms/b-cm
nuclides[name] = (name, density)
else:
raise RuntimeError(
'Volume information is needed to calculate microscopic '
f'cross sections for cell {self.id}. This can be done by '
'running a stochastic volume calculation via the '
'openmc.VolumeCalculation object')
return nuclides
[docs] def get_all_cells(self, memo=None):
"""Return all cells that are contained within this one if it is filled with a
universe or lattice
Returns
-------
cells : dict
Dictionary whose keys are cell IDs and values are :class:`Cell`
instances
"""
if memo is None:
memo = set()
elif self in memo:
return {}
memo.add(self)
cells = {}
if self.fill_type in ('universe', 'lattice'):
cells.update(self.fill.get_all_cells(memo))
return cells
[docs] def get_all_materials(self, memo=None):
"""Return all materials that are contained within the cell
Returns
-------
materials : dict
Dictionary whose keys are material IDs and values are
:class:`Material` instances
"""
materials = {}
if self.fill_type == 'material':
materials[self.fill.id] = self.fill
elif self.fill_type == 'distribmat':
for m in self.fill:
if m is not None:
materials[m.id] = m
else:
# Append all Cells in each Cell in the Universe to the dictionary
cells = self.get_all_cells(memo)
for cell in cells.values():
materials.update(cell.get_all_materials(memo))
return materials
[docs] def get_all_universes(self, memo=None):
"""Return all universes that are contained within this one if any of
its cells are filled with a universe or lattice.
Returns
-------
universes : dict
Dictionary whose keys are universe IDs and values are
:class:`Universe` instances
"""
if memo is None:
memo = set()
if self in memo:
return {}
memo.add(self)
universes = {}
if self.fill_type == 'universe':
universes[self.fill.id] = self.fill
universes.update(self.fill.get_all_universes(memo))
elif self.fill_type == 'lattice':
universes.update(self.fill.get_all_universes(memo))
return universes
[docs] def clone(self, clone_materials=True, clone_regions=True, memo=None):
"""Create a copy of this cell with a new unique ID, and clones
the cell's region and fill.
Parameters
----------
clone_materials : bool
Whether to create separate copies of the materials filling cells
contained in this cell, or the material filling this cell.
clone_regions : bool
Whether to create separate copies of the regions bounding cells
contained in this cell, and the region bounding this cell.
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 : openmc.Cell
The clone of this cell
"""
if memo is None:
memo = {}
# If no memoize'd clone exists, instantiate one
if self not in memo:
# Temporarily remove paths
paths = self._paths
self._paths = None
clone = openmc.Cell(name=self.name)
clone.volume = self.volume
if self.temperature is not None:
clone.temperature = self.temperature
if self.translation is not None:
clone.translation = self.translation
if self.rotation is not None:
clone.rotation = self.rotation
clone._num_instances = None
# Restore paths on original instance
self._paths = paths
if self.region is not None:
if clone_regions:
clone.region = self.region.clone(memo)
else:
clone.region = self.region
if self.fill is not None:
if self.fill_type == 'distribmat':
if not clone_materials:
clone.fill = self.fill
else:
clone.fill = [fill.clone(memo) if fill is not None else
None for fill in self.fill]
elif self.fill_type == 'material':
if not clone_materials:
clone.fill = self.fill
else:
clone.fill = self.fill.clone(memo)
else:
clone.fill = self.fill.clone(clone_materials,
clone_regions, memo)
# Memoize the clone
memo[self] = clone
return memo[self]
[docs] @add_plot_params
def plot(self, *args, **kwargs):
"""Display a slice plot of the cell.
.. versionadded:: 0.14.0
"""
# Create dummy universe but preserve used_ids
next_id = openmc.Universe.next_id
u = openmc.Universe(cells=[self])
openmc.Universe.used_ids.remove(u.id)
openmc.Universe.next_id = next_id
return u.plot(*args, **kwargs)
[docs] def create_xml_subelement(self, xml_element, memo=None):
"""Add the cell's xml representation to an incoming xml element
Parameters
----------
xml_element : lxml.etree._Element
XML element to be added to
memo : set or None
A set of object IDs representing geometry entities already
written to ``xml_element``. This parameter is used internally
and should not be specified by users.
Returns
-------
None
"""
element = ET.Element("cell")
element.set("id", str(self.id))
if len(self._name) > 0:
element.set("name", str(self.name))
if self.fill_type == 'void':
element.set("material", "void")
elif self.fill_type == 'material':
element.set("material", str(self.fill.id))
elif self.fill_type == 'distribmat':
element.set("material", ' '.join(['void' if m is None else str(m.id)
for m in self.fill]))
elif self.fill_type in ('universe', 'lattice'):
element.set("fill", str(self.fill.id))
self.fill.create_xml_subelement(xml_element, memo)
if self.region is not None:
# Set the region attribute with the region specification
region = str(self.region)
if region.startswith('('):
region = region[1:-1]
if len(region) > 0:
element.set("region", region)
# Only surfaces that appear in a region are added to the geometry
# file, so the appropriate check is performed here. First we create
# a function which is called recursively to navigate through the CSG
# tree. When it reaches a leaf (a Halfspace), it creates a <surface>
# element for the corresponding surface if none has been created
# thus far.
def create_surface_elements(node, element, memo=None):
if isinstance(node, Halfspace):
if memo is None:
memo = set()
elif node.surface in memo:
return
memo.add(node.surface)
xml_element.append(node.surface.to_xml_element())
elif isinstance(node, Complement):
create_surface_elements(node.node, element, memo)
else:
for subnode in node:
create_surface_elements(subnode, element, memo)
# Call the recursive function from the top node
create_surface_elements(self.region, xml_element, memo)
if self.temperature is not None:
if isinstance(self.temperature, Iterable):
element.set("temperature", ' '.join(
str(t) for t in self.temperature))
else:
element.set("temperature", str(self.temperature))
if self.translation is not None:
element.set("translation", ' '.join(map(str, self.translation)))
if self.rotation is not None:
element.set("rotation", ' '.join(map(str, self.rotation.ravel())))
if self.volume is not None:
element.set("volume", str(self.volume))
return element
[docs] @classmethod
def from_xml_element(cls, elem, surfaces, materials, get_universe):
"""Generate cell from XML element
Parameters
----------
elem : lxml.etree._Element
`<cell>` element
surfaces : dict
Dictionary mapping surface IDs to :class:`openmc.Surface` instances
materials : dict
Dictionary mapping material ID strings to :class:`openmc.Material`
instances (defined in :meth:`openmc.Geometry.from_xml`)
get_universe : function
Function returning universe (defined in
:meth:`openmc.Geometry.from_xml`)
Returns
-------
openmc.Cell
Cell instance
"""
cell_id = int(get_text(elem, 'id'))
name = get_text(elem, 'name')
c = cls(cell_id, name)
# Assign material/distributed materials or fill
mat_text = get_text(elem, 'material')
if mat_text is not None:
mat_ids = mat_text.split()
if len(mat_ids) > 1:
c.fill = [materials[i] for i in mat_ids]
else:
c.fill = materials[mat_ids[0]]
else:
fill_id = int(get_text(elem, 'fill'))
c.fill = get_universe(fill_id)
# Assign region
region = get_text(elem, 'region')
if region is not None:
c.region = Region.from_expression(region, surfaces)
# Check for other attributes
t = get_text(elem, 'temperature')
if t is not None:
if ' ' in t:
c.temperature = [float(t_i) for t_i in t.split()]
else:
c.temperature = float(t)
v = get_text(elem, 'volume')
if v is not None:
c.volume = float(v)
for key in ('temperature', 'rotation', 'translation'):
value = get_text(elem, key)
if value is not None:
values = [float(x) for x in value.split()]
if key == 'rotation' and len(values) == 9:
values = np.array(values).reshape(3, 3)
setattr(c, key, values)
# Add this cell to appropriate universe
univ_id = int(get_text(elem, 'universe', 0))
get_universe(univ_id).add_cell(c)
return c