mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-27 13:45:36 -04:00
Merge remote-tracking branch 'upstream/develop' into eq
This commit is contained in:
Adam Nelson
commit
9a3cec1dfb
17 changed files with 508 additions and 238 deletions
|
|
@ -204,20 +204,22 @@ should be used:
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|||
Compiling with MPI
|
||||
++++++++++++++++++
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||||
|
||||
To compile with MPI, set the :envvar:`FC` environment variable to the path to
|
||||
the MPI Fortran wrapper. For example, in a bash shell:
|
||||
To compile with MPI, set the :envvar:`FC` and :envvar:`CC` environment variables
|
||||
to the path to the MPI Fortran and C wrappers, respectively. For example, in a
|
||||
bash shell:
|
||||
|
||||
.. code-block:: sh
|
||||
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||||
export FC=mpif90
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||||
export CC=mpicc
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||||
cmake /path/to/openmc
|
||||
|
||||
Note that in many shells, an environment variable can be set for a single
|
||||
command, i.e.
|
||||
Note that in many shells, environment variables can be set for a single command,
|
||||
i.e.
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
FC=mpif90 cmake /path/to/openmc
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||||
FC=mpif90 CC=mpicc cmake /path/to/openmc
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||||
|
||||
Selecting HDF5 Installation
|
||||
+++++++++++++++++++++++++++
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||||
|
|
@ -343,7 +345,7 @@ compiler, it is necessary to specify that all objects be compiled with the
|
|||
.. code-block:: sh
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||||
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mkdir build && cd build
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FC=ifort FFLAGS=-mmic cmake -Dopenmp=on ..
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FC=ifort CC=icc FFLAGS=-mmic cmake -Dopenmp=on ..
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||||
make
|
||||
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||||
Note that unless an HDF5 build for the Intel Xeon Phi is already on your target
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|
|
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@ -34,6 +34,7 @@ _THERMAL_NAMES = {'al': 'c_Al27', 'al27': 'c_Al27',
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'orthod': 'c_ortho_D', 'dortho': 'c_ortho_D',
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'orthoh': 'c_ortho_H', 'hortho': 'c_ortho_H',
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'ouo2': 'c_O_in_UO2', 'o2-u': 'c_O_in_UO2', 'o2/u': 'c_O_in_UO2',
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'sio2': 'c_SiO2',
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'parad': 'c_para_D', 'dpara': 'c_para_D',
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'parah': 'c_para_H', 'hpara': 'c_para_H',
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'sch4': 'c_solid_CH4', 'smeth': 'c_solid_CH4',
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|
|
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|
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@ -376,7 +376,7 @@ class Filter(object):
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cell instance ID for 'distribcell' Filters. The bin is a 2-tuple of
|
||||
floats for 'energy' and 'energyout' filters corresponding to the
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energy boundaries of the bin of interest. The bin is an (x,y,z)
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||||
3-tuple for 'mesh' filters corresponding to the mesh cell
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||||
3-tuple for 'mesh' filters corresponding to the mesh cell of
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||||
interest.
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||||
|
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Returns
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|
|
|
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|
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@ -30,7 +30,7 @@ class Macroscopic(object):
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self._name = ''
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self._xs = None
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# Set the Material class attributes
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# Set the Macroscopic class attributes
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self.name = name
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|
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if xs is not None:
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|
|
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124
openmc/mesh.py
124
openmc/mesh.py
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@ -6,6 +6,7 @@ import sys
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import numpy as np
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import openmc.checkvalue as cv
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import openmc
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|
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if sys.version_info[0] >= 3:
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||||
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@ -181,6 +182,33 @@ class Mesh(object):
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string += '{0: <16}{1}{2}\n'.format('\tPixels', '=\t', self._width)
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return string
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||||
|
||||
def cell_generator(self):
|
||||
"""Generator function to traverse through every [i,j,k] index
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||||
of the mesh.
|
||||
|
||||
For example the following code:
|
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for mesh_index in mymesh.cell_generator():
|
||||
print mesh_index
|
||||
|
||||
will produce the following output for a 3-D 2x2x2 mesh in mymesh:
|
||||
[1, 1, 1]
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[1, 1, 2]
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||||
[1, 2, 1]
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||||
[1, 2, 2]
|
||||
...
|
||||
|
||||
"""
|
||||
|
||||
if len(self.dimension) == 2:
|
||||
for x in range(self.dimension[0]):
|
||||
for y in range(self.dimension[1]):
|
||||
yield [x + 1, y + 1, 1]
|
||||
else:
|
||||
for x in range(self.dimension[0]):
|
||||
for y in range(self.dimension[1]):
|
||||
for z in range(self.dimension[2]):
|
||||
yield [x + 1, y + 1, z + 1]
|
||||
|
||||
def get_mesh_xml(self):
|
||||
"""Return XML representation of the mesh
|
||||
|
||||
|
|
@ -210,3 +238,99 @@ class Mesh(object):
|
|||
subelement.text = ' '.join(map(str, self._width))
|
||||
|
||||
return element
|
||||
|
||||
def build_cells(self, bc=['reflective'] * 6):
|
||||
"""Generates a lattice of universes with the same dimensionality
|
||||
as the mesh object. The individual cells/universes produced
|
||||
will not have material definitions applied and so downstream code
|
||||
will have to apply that information.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
bc : iterable of {'reflective', 'periodic', 'transmission', or 'vacuum'}
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||||
Boundary conditions for each of the four faces of a rectangle
|
||||
(if aplying to a 2D mesh) or six faces of a parallelepiped
|
||||
(if applying to a 3D mesh) provided in the following order:
|
||||
[x min, x max, y min, y max, z min, z max]. 2-D cells do not
|
||||
contain the z min and z max entries.
|
||||
|
||||
Returns
|
||||
-------
|
||||
root_cell : openmc.Cell
|
||||
The cell containing the lattice representing the mesh geometry;
|
||||
this cell is a single parallelepiped with boundaries matching
|
||||
the outermost mesh boundary with the boundary conditions from bc
|
||||
applied.
|
||||
cells : iterable of openmc.Cell
|
||||
The list of cells within each lattice position mimicking the mesh
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||||
geometry.
|
||||
|
||||
"""
|
||||
|
||||
twod = len(self.dimension) == 2
|
||||
cv.check_length('bc', bc, length_min=4, length_max=6)
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for entry in bc:
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cv.check_value('bc', entry, ['transmission', 'vacuum',
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'reflective', 'periodic'])
|
||||
|
||||
# Build the cell which will contain the lattice
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xplanes = [openmc.XPlane(x0=self.lower_left[0],
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||||
boundary_type=bc[0]),
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||||
openmc.XPlane(x0=self.upper_right[0],
|
||||
boundary_type=bc[1])]
|
||||
yplanes = [openmc.YPlane(y0=self.lower_left[1],
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||||
boundary_type=bc[2]),
|
||||
openmc.YPlane(y0=self.upper_right[1],
|
||||
boundary_type=bc[3])]
|
||||
if twod:
|
||||
zplanes = [openmc.ZPlane(z0=np.finfo(np.float).min,
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||||
boundary_type='reflective'),
|
||||
openmc.ZPlane(z0=np.finfo(np.float).max,
|
||||
boundary_type='reflective')]
|
||||
else:
|
||||
zplanes = [openmc.ZPlane(z0=self.lower_left[2],
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||||
boundary_type=bc[4]),
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||||
openmc.ZPlane(z0=self.upper_right[2],
|
||||
boundary_type=bc[5])]
|
||||
root_cell = openmc.Cell()
|
||||
root_cell.region = ((+xplanes[0] & -xplanes[1]) &
|
||||
(+yplanes[0] & -yplanes[1]) &
|
||||
(+zplanes[0] & -zplanes[1]))
|
||||
|
||||
# Build the universes which will be used for each of the [i,j,k]
|
||||
# locations within the mesh.
|
||||
# We will also have to build cells to assign to these universes
|
||||
universes = np.ndarray(self.dimension[::-1], dtype=np.object)
|
||||
cells = []
|
||||
for [i, j, k] in self.cell_generator():
|
||||
if twod:
|
||||
universes[j - 1, i - 1] = openmc.Universe()
|
||||
cells.append(openmc.Cell())
|
||||
universes[j - 1, i - 1].add_cells([cells[-1]])
|
||||
else:
|
||||
universes[k - 1, j - 1, i - 1] = openmc.Universe()
|
||||
cells.append(openmc.Cell())
|
||||
universes[k - 1, j - 1, i - 1].add_cells([cells[-1]])
|
||||
|
||||
lattice = openmc.RectLattice()
|
||||
lattice.lower_left = self.lower_left
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||||
|
||||
if self.width is not None:
|
||||
lattice.pitch = self.width
|
||||
else:
|
||||
dx = ((self.upper_right[0] - self.lower_left[0]) /
|
||||
self.dimension[0])
|
||||
dy = ((self.upper_right[1] - self.lower_left[1]) /
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||||
self.dimension[1])
|
||||
if twod:
|
||||
lattice.pitch = [dx, dy]
|
||||
else:
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||||
dz = ((self.upper_right[2] - self.lower_left[2]) /
|
||||
self.dimension[2])
|
||||
lattice.pitch = [dx, dy, dz]
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||||
lattice.universes = universes
|
||||
|
||||
# Fill Cell with the Lattice
|
||||
root_cell.fill = lattice
|
||||
|
||||
return root_cell, cells
|
||||
|
|
|
|||
|
|
@ -823,7 +823,7 @@ class Library(object):
|
|||
|
||||
def get_xsdata(self, domain, xsdata_name, nuclide='total', xs_type='macro',
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xs_id='1m', order=None, tabular_legendre=None,
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||||
tabular_points=33):
|
||||
tabular_points=33, subdomain=None):
|
||||
"""Generates an openmc.XSdata object describing a multi-group cross section
|
||||
data set for eventual combination in to an openmc.MGXSLibrary object
|
||||
(i.e., the library).
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||||
|
|
@ -859,6 +859,12 @@ class Library(object):
|
|||
parameter is set to `True`. In this case, this parameter sets the
|
||||
number of equally-spaced points in the domain of [-1,1] to be used
|
||||
in building the tabular distribution. Default is `33`.
|
||||
subdomain : iterable of int
|
||||
This parameter is not used unless using a mesh domain. In that
|
||||
case, the subdomain is an [i,j,k] index (1-based indexing) of the
|
||||
mesh cell of interest in the openmc.Mesh object. Note:
|
||||
this parameter currently only supports subdomains within a mesh,
|
||||
and not the subdomains of a distribcell.
|
||||
|
||||
Returns
|
||||
-------
|
||||
|
|
@ -878,7 +884,7 @@ class Library(object):
|
|||
"""
|
||||
|
||||
cv.check_type('domain', domain, (openmc.Material, openmc.Cell,
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||||
openmc.Cell, openmc.Mesh))
|
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openmc.Universe, openmc.Mesh))
|
||||
cv.check_type('xsdata_name', xsdata_name, basestring)
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||||
cv.check_type('nuclide', nuclide, basestring)
|
||||
cv.check_value('xs_type', xs_type, ['macro', 'micro'])
|
||||
|
|
@ -891,6 +897,9 @@ class Library(object):
|
|||
(type(None), bool))
|
||||
if tabular_points is not None:
|
||||
cv.check_greater_than('tabular_points', tabular_points, 1)
|
||||
if subdomain is not None:
|
||||
cv.check_iterable_type('subdomain', subdomain, Integral,
|
||||
max_depth=3)
|
||||
|
||||
# Make sure statepoint has been loaded
|
||||
if self._sp_filename is None:
|
||||
|
|
@ -926,52 +935,66 @@ class Library(object):
|
|||
xsdata.zaid = self._nuclides[nuclide][0]
|
||||
xsdata.awr = self._nuclides[nuclide][1]
|
||||
|
||||
if subdomain is None:
|
||||
subdomain = 'all'
|
||||
else:
|
||||
subdomain = [subdomain]
|
||||
|
||||
# Now get xs data itself
|
||||
if 'nu-transport' in self.mgxs_types and self.correction == 'P0':
|
||||
mymgxs = self.get_mgxs(domain, 'nu-transport')
|
||||
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide])
|
||||
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
|
||||
subdomains=subdomain)
|
||||
elif 'total' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'total')
|
||||
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide])
|
||||
xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
if 'absorption' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'absorption')
|
||||
xsdata.set_absorption_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
if 'fission' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'fission')
|
||||
xsdata.set_fission_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide], subdomain=subdomain)
|
||||
if 'kappa-fission' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'kappa-fission')
|
||||
xsdata.set_kappa_fission_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
# For chi and nu-fission we can either have only a nu-fission matrix
|
||||
# provided, or vectors of chi and nu-fission provided
|
||||
if 'nu-fission matrix' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'nu-fission matrix')
|
||||
xsdata.set_nu_fission_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
else:
|
||||
if 'chi' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'chi')
|
||||
xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide])
|
||||
xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
if 'nu-fission' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'nu-fission')
|
||||
xsdata.set_nu_fission_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
# If multiplicity matrix is available, prefer that
|
||||
if 'multiplicity matrix' in self.mgxs_types:
|
||||
mymgxs = self.get_mgxs(domain, 'multiplicity matrix')
|
||||
xsdata.set_multiplicity_mgxs(mymgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
using_multiplicity = True
|
||||
# multiplicity wil fall back to using scatter and nu-scatter
|
||||
# multiplicity will fall back to using scatter and nu-scatter
|
||||
elif ((('scatter matrix' in self.mgxs_types) and
|
||||
('nu-scatter matrix' in self.mgxs_types))):
|
||||
scatt_mgxs = self.get_mgxs(domain, 'scatter matrix')
|
||||
nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix')
|
||||
xsdata.set_multiplicity_mgxs(nuscatt_mgxs, scatt_mgxs,
|
||||
xs_type=xs_type, nuclide=[nuclide])
|
||||
xs_type=xs_type, nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
using_multiplicity = True
|
||||
else:
|
||||
using_multiplicity = False
|
||||
|
|
@ -979,12 +1002,13 @@ class Library(object):
|
|||
if using_multiplicity:
|
||||
nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix')
|
||||
xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide], subdomain=subdomain)
|
||||
else:
|
||||
if 'nu-scatter matrix' in self.mgxs_types:
|
||||
nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix')
|
||||
xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type,
|
||||
nuclide=[nuclide])
|
||||
nuclide=[nuclide],
|
||||
subdomain=subdomain)
|
||||
|
||||
# Since we are not using multiplicity, then
|
||||
# scattering multiplication (nu-scatter) must be
|
||||
|
|
@ -1055,15 +1079,6 @@ class Library(object):
|
|||
cv.check_value('xs_type', xs_type, ['macro', 'micro'])
|
||||
if xsdata_names is not None:
|
||||
cv.check_iterable_type('xsdata_names', xsdata_names, basestring)
|
||||
if xs_ids is not None:
|
||||
if isinstance(xs_ids, basestring):
|
||||
# If we only have a string lets convert it now to a list
|
||||
# of strings.
|
||||
xs_ids = [xs_ids for i in range(len(self.domains))]
|
||||
else:
|
||||
cv.check_iterable_type('xs_ids', xs_ids, basestring)
|
||||
else:
|
||||
xs_ids = ['1m' for i in range(len(self.domains))]
|
||||
|
||||
# If gathering material-specific data, set the xs_type to macro
|
||||
if not self.by_nuclide:
|
||||
|
|
@ -1072,32 +1087,78 @@ class Library(object):
|
|||
# Initialize file
|
||||
mgxs_file = openmc.MGXSLibrary(self.energy_groups)
|
||||
|
||||
# Create the xsdata object and add it to the mgxs_file
|
||||
for i, domain in enumerate(self.domains):
|
||||
if self.by_nuclide:
|
||||
nuclides = domain.get_nuclides()
|
||||
# Get the number of domains to size arrays with
|
||||
if self.domain_type is 'mesh':
|
||||
num_domains = np.sum(d.num_mesh_cells for d in self.domains)
|
||||
else:
|
||||
num_domains = len(self.domains)
|
||||
|
||||
# Set id names
|
||||
if xs_ids is not None:
|
||||
if isinstance(xs_ids, basestring):
|
||||
# If we only have a string lets convert it now to a list
|
||||
# of strings.
|
||||
all_xs_ids = [xs_ids] * num_domains
|
||||
else:
|
||||
nuclides = ['total']
|
||||
for nuclide in nuclides:
|
||||
# Build & add metadata to XSdata object
|
||||
if xsdata_names is None:
|
||||
xsdata_name = 'set' + str(i + 1)
|
||||
cv.check_iterable_type('xs_ids', xs_ids, basestring)
|
||||
cv.check_length('xs_ids', xs_ids, num_domains, num_domains)
|
||||
all_xs_ids = xs_ids
|
||||
|
||||
else:
|
||||
all_xs_ids = ['1m'] * num_domains
|
||||
|
||||
if self.domain_type == 'mesh':
|
||||
# Create the xsdata objects and add to the mgxs_file
|
||||
i = 0
|
||||
for domain in self.domains:
|
||||
if self.by_nuclide:
|
||||
raise NotImplementedError("Mesh domains do not currently "
|
||||
"support nuclidic tallies")
|
||||
for subdomain in domain.cell_generator():
|
||||
# Build & add metadata to XSdata object
|
||||
if xsdata_names is None:
|
||||
xsdata_name = 'set' + str(i + 1)
|
||||
else:
|
||||
xsdata_name = xsdata_names[i]
|
||||
|
||||
# Create XSdata and Macroscopic for this domain
|
||||
xsdata = self.get_xsdata(domain, xsdata_name,
|
||||
xs_id=all_xs_ids[i],
|
||||
tabular_legendre=tabular_legendre,
|
||||
tabular_points=tabular_points,
|
||||
subdomain=subdomain)
|
||||
mgxs_file.add_xsdata(xsdata)
|
||||
i += 1
|
||||
|
||||
else:
|
||||
# Create the xsdata object and add it to the mgxs_file
|
||||
for i, domain in enumerate(self.domains):
|
||||
if self.by_nuclide:
|
||||
nuclides = domain.get_nuclides()
|
||||
else:
|
||||
xsdata_name = xsdata_names[i]
|
||||
if nuclide is not 'total':
|
||||
xsdata_name += '_' + nuclide
|
||||
nuclides = ['total']
|
||||
for nuclide in nuclides:
|
||||
# Build & add metadata to XSdata object
|
||||
if xsdata_names is None:
|
||||
xsdata_name = 'set' + str(i + 1)
|
||||
else:
|
||||
xsdata_name = xsdata_names[i]
|
||||
if nuclide is not 'total':
|
||||
xsdata_name += '_' + nuclide
|
||||
|
||||
xsdata = self.get_xsdata(domain, xsdata_name, nuclide=nuclide,
|
||||
xs_type=xs_type, xs_id=xs_ids[i],
|
||||
tabular_legendre=tabular_legendre,
|
||||
tabular_points=tabular_points)
|
||||
xsdata = self.get_xsdata(domain, xsdata_name,
|
||||
nuclide=nuclide, xs_type=xs_type,
|
||||
xs_id=all_xs_ids[i],
|
||||
tabular_legendre=tabular_legendre,
|
||||
tabular_points=tabular_points)
|
||||
|
||||
mgxs_file.add_xsdata(xsdata)
|
||||
mgxs_file.add_xsdata(xsdata)
|
||||
|
||||
return mgxs_file
|
||||
|
||||
def create_mg_mode(self, xsdata_names=None, xs_ids=None,
|
||||
tabular_legendre=None, tabular_points=33):
|
||||
tabular_legendre=None, tabular_points=33,
|
||||
bc=['reflective'] * 6):
|
||||
"""Creates an openmc.MGXSLibrary object to contain the MGXS data for the
|
||||
Multi-Group mode of OpenMC as well as the associated openmc.Materials
|
||||
and openmc.Geometry objects. The created Geometry is the same as that
|
||||
|
|
@ -1127,6 +1188,12 @@ class Library(object):
|
|||
parameter is set to `True`. In this case, this parameter sets the
|
||||
number of equally-spaced points in the domain of [-1,1] to be used
|
||||
in building the tabular distribution. Default is `33`.
|
||||
bc : iterable of {'reflective', 'periodic', 'transmission', or 'vacuum'}
|
||||
Boundary conditions for each of the four faces of a rectangle
|
||||
(if applying to a 2D mesh) or six faces of a parallelepiped
|
||||
(if applying to a 3D mesh) provided in the following order:
|
||||
[x min, x max, y min, y max, z min, z max]. 2-D cells do not
|
||||
contain the z min and z max entries.
|
||||
|
||||
Returns
|
||||
-------
|
||||
|
|
@ -1157,62 +1224,77 @@ class Library(object):
|
|||
# multi-group cross section types
|
||||
self.check_library_for_openmc_mgxs()
|
||||
|
||||
if xsdata_names is not None:
|
||||
cv.check_iterable_type('xsdata_names', xsdata_names, basestring)
|
||||
if xs_ids is not None:
|
||||
if isinstance(xs_ids, basestring):
|
||||
# If we only have a string lets convert it now to a list
|
||||
# of strings.
|
||||
xs_ids = [xs_ids for i in range(len(self.domains))]
|
||||
else:
|
||||
cv.check_iterable_type('xs_ids', xs_ids, basestring)
|
||||
# If the domain type is a mesh, then there can only be one domain for
|
||||
# this method. This is because we can build a model automatically if
|
||||
# the user provided multiple mesh domains for library generation since
|
||||
# the multiple meshes could be overlapping or in disparate regions
|
||||
# of the continuous energy model. The next step makes sure there is
|
||||
# only one before continuing.
|
||||
if self.domain_type == 'mesh':
|
||||
cv.check_length("domains", self.domains, 1, 1)
|
||||
|
||||
# Get the MGXS File Data
|
||||
mgxs_file = self.create_mg_library('macro', xsdata_names, xs_ids,
|
||||
tabular_legendre, tabular_points)
|
||||
|
||||
# Now move on the creating the geometry and assigning materials
|
||||
if self.domain_type == 'mesh':
|
||||
root = openmc.Universe(name='root', universe_id=0)
|
||||
|
||||
# Add cells representative of the mesh with reflective BC
|
||||
root_cell, cells = \
|
||||
self.domains[0].build_cells(bc)
|
||||
root.add_cell(root_cell)
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = root
|
||||
materials = openmc.Materials()
|
||||
|
||||
for i, subdomain in enumerate(self.domains[0].cell_generator()):
|
||||
xsdata = mgxs_file.xsdatas[i]
|
||||
[name, id] = xsdata.name.split('.')
|
||||
# Build the macroscopic and assign it to the cell of
|
||||
# interest
|
||||
macroscopic = openmc.Macroscopic(name=name, xs=id)
|
||||
|
||||
# Create Material and add to collection
|
||||
material = openmc.Material(name=xsdata.name)
|
||||
material.add_macroscopic(macroscopic)
|
||||
materials.append(material)
|
||||
|
||||
# Set the materials for each of the universes
|
||||
cells[i].fill = materials[i]
|
||||
|
||||
else:
|
||||
xs_ids = ['1m' for i in range(len(self.domains))]
|
||||
xs_type = 'macro'
|
||||
# Create a copy of the Geometry for these Macroscopics
|
||||
geometry = copy.deepcopy(self.openmc_geometry)
|
||||
materials = openmc.Materials()
|
||||
|
||||
# Initialize MGXS File
|
||||
mgxs_file = openmc.MGXSLibrary(self.energy_groups)
|
||||
# Get all Cells from the Geometry for differentiation
|
||||
all_cells = geometry.get_all_material_cells()
|
||||
|
||||
# Create a copy of the Geometry to differentiate for these Macroscopics
|
||||
geometry = copy.deepcopy(self.openmc_geometry)
|
||||
materials = openmc.Materials()
|
||||
# Create the xsdata object and add it to the mgxs_file
|
||||
for i, domain in enumerate(self.domains):
|
||||
xsdata = mgxs_file.xsdatas[i]
|
||||
[name, id] = xsdata.name.split('.')
|
||||
|
||||
# Get all Cells from the Geometry for differentiation
|
||||
all_cells = geometry.get_all_material_cells()
|
||||
macroscopic = openmc.Macroscopic(name=name, xs=id)
|
||||
|
||||
# Create the xsdata object and add it to the mgxs_file
|
||||
for i, domain in enumerate(self.domains):
|
||||
# Create Material and add to collection
|
||||
material = openmc.Material(name=xsdata.name)
|
||||
material.add_macroscopic(macroscopic)
|
||||
materials.append(material)
|
||||
|
||||
# Build & add metadata to XSdata object
|
||||
if xsdata_names is None:
|
||||
xsdata_name = 'set' + str(i + 1)
|
||||
else:
|
||||
xsdata_name = xsdata_names[i]
|
||||
# Differentiate Geometry with new Material
|
||||
if self.domain_type == 'material':
|
||||
# Fill all appropriate Cells with new Material
|
||||
for cell in all_cells:
|
||||
if cell.fill.id == domain.id:
|
||||
cell.fill = material
|
||||
|
||||
# Create XSdata and Macroscopic for this domain
|
||||
xsdata = self.get_xsdata(domain, xsdata_name, nuclide='total',
|
||||
xs_type=xs_type, xs_id=xs_ids[i],
|
||||
tabular_legendre=tabular_legendre,
|
||||
tabular_points=tabular_points)
|
||||
mgxs_file.add_xsdata(xsdata)
|
||||
macroscopic = openmc.Macroscopic(name=xsdata_name, xs=xs_ids[i])
|
||||
|
||||
# Create Material and add to collection
|
||||
material = openmc.Material(name=xsdata_name + '.' + xs_ids[i])
|
||||
material.add_macroscopic(macroscopic)
|
||||
materials.append(material)
|
||||
|
||||
# Differentiate Geometry with new Material
|
||||
if self.domain_type == 'material':
|
||||
# Fill all appropriate Cells with new Material
|
||||
for cell in all_cells:
|
||||
if cell.fill.id == domain.id:
|
||||
cell.fill = material
|
||||
|
||||
elif self.domain_type == 'cell':
|
||||
for cell in all_cells:
|
||||
if cell.id == domain.id:
|
||||
cell.fill = material
|
||||
elif self.domain_type == 'cell':
|
||||
for cell in all_cells:
|
||||
if cell.id == domain.id:
|
||||
cell.fill = material
|
||||
|
||||
return mgxs_file, materials, geometry
|
||||
|
||||
|
|
|
|||
|
|
@ -793,7 +793,8 @@ class MDGXS(MGXS):
|
|||
|
||||
df.rename(columns={'energyout low [MeV]': 'group out'},
|
||||
inplace=True)
|
||||
out_groups = np.tile(all_groups, int(df.shape[0] / all_groups.size))
|
||||
out_groups = np.repeat(all_groups, self.xs_tally.num_scores)
|
||||
out_groups = np.tile(out_groups, int(df.shape[0] / out_groups.size))
|
||||
df['group out'] = out_groups
|
||||
del df['energyout high [MeV]']
|
||||
columns = ['group in', 'group out']
|
||||
|
|
|
|||
|
|
@ -548,12 +548,6 @@ class MGXS(object):
|
|||
float
|
||||
The atomic number density (atom/b-cm) for the nuclide of interest
|
||||
|
||||
Raises
|
||||
-------
|
||||
ValueError
|
||||
When the density is requested for a nuclide which is not found in
|
||||
the spatial domain.
|
||||
|
||||
"""
|
||||
|
||||
cv.check_type('nuclide', nuclide, basestring)
|
||||
|
|
@ -561,13 +555,7 @@ class MGXS(object):
|
|||
# Get list of all nuclides in the spatial domain
|
||||
nuclides = self.domain.get_nuclide_densities()
|
||||
|
||||
if nuclide not in nuclides:
|
||||
msg = 'Unable to get density for nuclide "{0}" which is not in ' \
|
||||
'{1} "{2}"'.format(nuclide, self.domain_type, self.domain.id)
|
||||
ValueError(msg)
|
||||
|
||||
density = nuclides[nuclide][1]
|
||||
return density
|
||||
return nuclides[nuclide][1] if nuclide in nuclides else 0.0
|
||||
|
||||
def get_nuclide_densities(self, nuclides='all'):
|
||||
"""Get an array of atomic number densities in units of atom/b-cm for all
|
||||
|
|
@ -789,7 +777,8 @@ class MGXS(object):
|
|||
|
||||
# Construct a collection of the domain filter bins
|
||||
if not isinstance(subdomains, basestring):
|
||||
cv.check_iterable_type('subdomains', subdomains, Integral, max_depth=3)
|
||||
cv.check_iterable_type('subdomains', subdomains, Integral,
|
||||
max_depth=3)
|
||||
for subdomain in subdomains:
|
||||
filters.append(self.domain_type)
|
||||
filter_bins.append((subdomain,))
|
||||
|
|
@ -1535,7 +1524,8 @@ class MGXS(object):
|
|||
|
||||
df.rename(columns={'energyout low [MeV]': 'group out'},
|
||||
inplace=True)
|
||||
out_groups = np.tile(all_groups, int(df.shape[0] / all_groups.size))
|
||||
out_groups = np.repeat(all_groups, self.xs_tally.num_scores)
|
||||
out_groups = np.tile(out_groups, int(df.shape[0] / out_groups.size))
|
||||
df['group out'] = out_groups
|
||||
del df['energyout high [MeV]']
|
||||
columns = ['group in', 'group out']
|
||||
|
|
@ -1573,6 +1563,10 @@ class MGXS(object):
|
|||
df['mean'] /= np.tile(densities, tile_factor)
|
||||
df['std. dev.'] /= np.tile(densities, tile_factor)
|
||||
|
||||
# Replace NaNs by zeros (happens if nuclide density is zero)
|
||||
df['mean'].replace(np.nan, 0.0, inplace=True)
|
||||
df['std. dev.'].replace(np.nan, 0.0, inplace=True)
|
||||
|
||||
# Sort the dataframe by domain type id (e.g., distribcell id) and
|
||||
# energy groups such that data is from fast to thermal
|
||||
if self.domain_type == 'mesh':
|
||||
|
|
|
|||
|
|
@ -603,7 +603,8 @@ class XSdata(object):
|
|||
if np.sum(self._nu_fission) > 0.0:
|
||||
self._fissionable = True
|
||||
|
||||
def set_total_mgxs(self, total, nuclide='total', xs_type='macro'):
|
||||
def set_total_mgxs(self, total, nuclide='total', xs_type='macro',
|
||||
subdomain='all'):
|
||||
"""This method allows for an openmc.mgxs.TotalXS or
|
||||
openmc.mgxs.TransportXS to be used to set the total cross section
|
||||
for this XSdata object.
|
||||
|
|
@ -619,6 +620,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -631,16 +635,17 @@ class XSdata(object):
|
|||
openmc.mgxs.TransportXS))
|
||||
check_value('energy_groups', total.energy_groups, [self.energy_groups])
|
||||
check_value('domain_type', total.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._total = total.get_xs(nuclides=nuclide, xs_type=xs_type)
|
||||
self._total = total.get_xs(nuclides=nuclide, xs_type=xs_type,
|
||||
subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
||||
def set_absorption_mgxs(self, absorption, nuclide='total',
|
||||
xs_type='macro'):
|
||||
xs_type='macro', subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.AbsorptionXS
|
||||
to be used to set the absorption cross section for this XSdata object.
|
||||
|
||||
|
|
@ -655,6 +660,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -667,16 +675,18 @@ class XSdata(object):
|
|||
check_value('energy_groups', absorption.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', absorption.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._absorption = absorption.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type)
|
||||
xs_type=xs_type,
|
||||
subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
||||
def set_fission_mgxs(self, fission, nuclide='total', xs_type='macro'):
|
||||
def set_fission_mgxs(self, fission, nuclide='total', xs_type='macro',
|
||||
subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.FissionXS
|
||||
to be used to set the fission cross section for this XSdata object.
|
||||
|
||||
|
|
@ -691,6 +701,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -703,17 +716,18 @@ class XSdata(object):
|
|||
check_value('energy_groups', fission.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', fission.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._fission = fission.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type)
|
||||
xs_type=xs_type,
|
||||
subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
||||
def set_nu_fission_mgxs(self, nu_fission, nuclide='total',
|
||||
xs_type='macro'):
|
||||
xs_type='macro', subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.NuFissionXS
|
||||
to be used to set the nu-fission cross section for this XSdata object.
|
||||
|
||||
|
|
@ -728,6 +742,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -741,11 +758,12 @@ class XSdata(object):
|
|||
check_value('energy_groups', nu_fission.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', nu_fission.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._nu_fission = nu_fission.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type)
|
||||
xs_type=xs_type,
|
||||
subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
|
@ -759,7 +777,7 @@ class XSdata(object):
|
|||
self._fissionable = True
|
||||
|
||||
def set_kappa_fission_mgxs(self, k_fission, nuclide='total',
|
||||
xs_type='macro'):
|
||||
xs_type='macro', subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.KappaFissionXS
|
||||
to be used to set the kappa-fission cross section for this XSdata
|
||||
object.
|
||||
|
|
@ -775,6 +793,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -787,16 +808,18 @@ class XSdata(object):
|
|||
check_value('energy_groups', k_fission.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', k_fission.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._kappa_fission = k_fission.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type)
|
||||
xs_type=xs_type,
|
||||
subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
||||
def set_chi_mgxs(self, chi, nuclide='total', xs_type='macro'):
|
||||
def set_chi_mgxs(self, chi, nuclide='total', xs_type='macro',
|
||||
subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.Chi
|
||||
to be used to set chi for this XSdata object.
|
||||
|
||||
|
|
@ -810,6 +833,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -827,11 +853,11 @@ class XSdata(object):
|
|||
check_type('chi', chi, openmc.mgxs.Chi)
|
||||
check_value('energy_groups', chi.energy_groups, [self.energy_groups])
|
||||
check_value('domain_type', chi.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
self._chi = chi.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type)
|
||||
xs_type=xs_type, subdomains=subdomain)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
|
@ -839,7 +865,8 @@ class XSdata(object):
|
|||
if self.use_chi is not None:
|
||||
self.use_chi = True
|
||||
|
||||
def set_scatter_mgxs(self, scatter, nuclide='total', xs_type='macro'):
|
||||
def set_scatter_mgxs(self, scatter, nuclide='total', xs_type='macro',
|
||||
subdomain=None):
|
||||
"""This method allows for an openmc.mgxs.ScatterMatrixXS
|
||||
to be used to set the scatter matrix cross section for this XSdata
|
||||
object. If the XSdata.order attribute has not yet been set, then
|
||||
|
|
@ -856,6 +883,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -868,7 +898,7 @@ class XSdata(object):
|
|||
check_value('energy_groups', scatter.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', scatter.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.scatt_type != 'legendre':
|
||||
msg = 'Anisotropic scattering representations other than ' \
|
||||
|
|
@ -892,16 +922,16 @@ class XSdata(object):
|
|||
self.energy_groups.num_groups,
|
||||
self.energy_groups.num_groups))
|
||||
for moment in range(self.num_orders):
|
||||
self._scatter[moment, :, :] = scatter.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type,
|
||||
moment=moment)
|
||||
self._scatter[moment, :, :] = \
|
||||
scatter.get_xs(nuclides=nuclide, xs_type=xs_type,
|
||||
moment=moment, subdomains=subdomain)
|
||||
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
raise ValueError(msg)
|
||||
|
||||
def set_multiplicity_mgxs(self, nuscatter, scatter=None, nuclide='total',
|
||||
xs_type='macro'):
|
||||
xs_type='macro', subdomain=None):
|
||||
"""This method allows for either the direct use of only an
|
||||
openmc.mgxs.MultiplicityMatrixXS OR an openmc.mgxs.NuScatterMatrixXS and
|
||||
openmc.mgxs.ScatterMatrixXS to be used to set the scattering
|
||||
|
|
@ -926,6 +956,9 @@ class XSdata(object):
|
|||
xs_type: {'macro', 'micro'}
|
||||
Provide the macro or micro cross section in units of cm^-1 or
|
||||
barns. Defaults to 'macro'.
|
||||
subdomain : iterable of int
|
||||
If the MGXS contains a mesh domain type, the subdomain parameter
|
||||
specifies which mesh cell (i.e., [i, j, k] index) to use.
|
||||
|
||||
See also
|
||||
--------
|
||||
|
|
@ -939,7 +972,7 @@ class XSdata(object):
|
|||
check_value('energy_groups', nuscatter.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', nuscatter.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
if scatter is not None:
|
||||
check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS)
|
||||
if isinstance(nuscatter, openmc.mgxs.MultiplicityMatrixXS):
|
||||
|
|
@ -950,16 +983,18 @@ class XSdata(object):
|
|||
check_value('energy_groups', scatter.energy_groups,
|
||||
[self.energy_groups])
|
||||
check_value('domain_type', scatter.domain_type,
|
||||
['universe', 'cell', 'material'])
|
||||
['universe', 'cell', 'material', 'mesh'])
|
||||
|
||||
if self.representation is 'isotropic':
|
||||
nuscatt = nuscatter.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type, moment=0)
|
||||
xs_type=xs_type, moment=0,
|
||||
subdomains=subdomain)
|
||||
if isinstance(nuscatter, openmc.mgxs.MultiplicityMatrixXS):
|
||||
self._multiplicity = nuscatt
|
||||
else:
|
||||
scatt = scatter.get_xs(nuclides=nuclide,
|
||||
xs_type=xs_type, moment=0)
|
||||
xs_type=xs_type, moment=0,
|
||||
subdomains=subdomain)
|
||||
self._multiplicity = np.divide(nuscatt, scatt)
|
||||
elif self.representation is 'angle':
|
||||
msg = 'Angular-Dependent MGXS have not yet been implemented'
|
||||
|
|
@ -1085,6 +1120,10 @@ class MGXSLibrary(object):
|
|||
def energy_groups(self):
|
||||
return self._energy_groups
|
||||
|
||||
@property
|
||||
def xsdatas(self):
|
||||
return self._xsdatas
|
||||
|
||||
@inverse_velocities.setter
|
||||
def inverse_velocities(self, inverse_velocities):
|
||||
check_type('inverse_velocities', inverse_velocities, Iterable, Real)
|
||||
|
|
|
|||
|
|
@ -997,13 +997,17 @@ def get_opencg_geometry(openmc_geometry):
|
|||
return opencg_geometry
|
||||
|
||||
|
||||
def get_openmc_geometry(opencg_geometry):
|
||||
def get_openmc_geometry(opencg_geometry, compatible=False):
|
||||
"""Return an OpenMC geometry corresponding to an OpenCG geometry.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
opencg_geometry : opencg.Geometry
|
||||
OpenCG geometry
|
||||
compatible : bool
|
||||
Whether the OpenCG geometry is compatible with OpenMC's geometric
|
||||
primitives. This should be set to False if the OpenCG geometry
|
||||
uses SquarePrism surfaces. False by default.
|
||||
|
||||
Returns
|
||||
-------
|
||||
|
|
@ -1019,9 +1023,6 @@ def get_openmc_geometry(opencg_geometry):
|
|||
opencg_geometry.assign_auto_ids()
|
||||
opencg_geometry = copy.deepcopy(opencg_geometry)
|
||||
|
||||
# Update Cell bounding boxes in Geometry
|
||||
opencg_geometry.update_bounding_boxes()
|
||||
|
||||
# Clear dictionaries and auto-generated ID
|
||||
OPENMC_SURFACES.clear()
|
||||
OPENCG_SURFACES.clear()
|
||||
|
|
@ -1033,12 +1034,13 @@ def get_openmc_geometry(opencg_geometry):
|
|||
OPENCG_LATTICES.clear()
|
||||
|
||||
# Make the entire geometry "compatible" before assigning auto IDs
|
||||
universes = opencg_geometry.get_all_universes()
|
||||
for universe in universes.values():
|
||||
if not isinstance(universe, opencg.Lattice):
|
||||
make_opencg_cells_compatible(universe)
|
||||
if not compatible:
|
||||
universes = opencg_geometry.get_all_universes()
|
||||
for universe in universes.values():
|
||||
if not isinstance(universe, opencg.Lattice):
|
||||
make_opencg_cells_compatible(universe)
|
||||
|
||||
opencg_geometry.assign_auto_ids()
|
||||
opencg_geometry.assign_auto_ids()
|
||||
|
||||
opencg_root_universe = opencg_geometry.root_universe
|
||||
openmc_root_universe = get_openmc_universe(opencg_root_universe)
|
||||
|
|
|
|||
|
|
@ -1,6 +1,7 @@
|
|||
from collections import Iterable, Mapping
|
||||
from numbers import Real, Integral
|
||||
from xml.etree import ElementTree as ET
|
||||
from warnings import warn
|
||||
|
||||
import numpy as np
|
||||
import pandas as pd
|
||||
|
|
@ -68,10 +69,26 @@ class VolumeCalculation(object):
|
|||
self.samples = samples
|
||||
|
||||
if lower_left is not None:
|
||||
self.lower_left = lower_left
|
||||
if upper_right is None:
|
||||
raise ValueError('Both lower-left and upper-right coordinates '
|
||||
'should be specified')
|
||||
|
||||
# For cell domains, try to compute bounding box and make sure
|
||||
# user-specified one is valid
|
||||
if self.domain_type == 'cell':
|
||||
for c in domains:
|
||||
if c.region is None:
|
||||
continue
|
||||
ll, ur = c.region.bounding_box
|
||||
if np.any(np.isinf(ll)) or np.any(np.isinf(ur)):
|
||||
continue
|
||||
if (np.any(np.asarray(lower_left) > ll) or
|
||||
np.any(np.asarray(upper_right) < ur)):
|
||||
warn("Specified bounding box is smaller than computed "
|
||||
"bounding box for cell {}. Volume calculation may "
|
||||
"be incorrect!".format(c.id))
|
||||
|
||||
self.lower_left = lower_left
|
||||
self.upper_right = upper_right
|
||||
else:
|
||||
if self.domain_type == 'cell':
|
||||
|
|
|
|||
|
|
@ -54,7 +54,8 @@ module constants
|
|||
|
||||
! Maximum number of external source spatial resamples to encounter before an
|
||||
! error is thrown.
|
||||
integer, parameter :: MAX_EXTSRC_RESAMPLES = 10000
|
||||
integer, parameter :: EXTSRC_REJECT_THRESHOLD = 10000
|
||||
real(8), parameter :: EXTSRC_REJECT_FRACTION = 0.05
|
||||
|
||||
! ============================================================================
|
||||
! PHYSICAL CONSTANTS
|
||||
|
|
|
|||
|
|
@ -153,7 +153,7 @@ element settings {
|
|||
attribute lower_left { list { xsd:double+ } }) &
|
||||
(element upper_right { list { xsd:double+ } } |
|
||||
attribute upper_right { list { xsd:double+ } })
|
||||
}+ &
|
||||
}* &
|
||||
|
||||
element uniform_fs{
|
||||
(element dimension { list { xsd:positiveInteger+ } } |
|
||||
|
|
|
|||
|
|
@ -625,7 +625,7 @@
|
|||
<data type="positiveInteger"/>
|
||||
</element>
|
||||
</optional>
|
||||
<oneOrMore>
|
||||
<zeroOrMore>
|
||||
<element name="volume_calc">
|
||||
<interleave>
|
||||
<choice>
|
||||
|
|
@ -694,7 +694,7 @@
|
|||
</choice>
|
||||
</interleave>
|
||||
</element>
|
||||
</oneOrMore>
|
||||
</zeroOrMore>
|
||||
<optional>
|
||||
<element name="uniform_fs">
|
||||
<interleave>
|
||||
|
|
|
|||
|
|
@ -107,7 +107,8 @@ contains
|
|||
real(8) :: r(3) ! sampled coordinates
|
||||
logical :: found ! Does the source particle exist within geometry?
|
||||
type(Particle) :: p ! Temporary particle for using find_cell
|
||||
integer, save :: num_resamples = 0 ! Number of resamples encountered
|
||||
integer, save :: n_accept = 0 ! Number of samples accepted
|
||||
integer, save :: n_reject = 0 ! Number of samples rejected
|
||||
|
||||
! Set weight to one by default
|
||||
site % wgt = ONE
|
||||
|
|
@ -143,13 +144,6 @@ contains
|
|||
|
||||
! Now search to see if location exists in geometry
|
||||
call find_cell(p, found)
|
||||
if (.not. found) then
|
||||
num_resamples = num_resamples + 1
|
||||
if (num_resamples == MAX_EXTSRC_RESAMPLES) then
|
||||
call fatal_error("Maximum number of external source spatial &
|
||||
&resamples reached!")
|
||||
end if
|
||||
end if
|
||||
|
||||
! Check if spatial site is in fissionable material
|
||||
select type (space => external_source(i) % space)
|
||||
|
|
@ -162,8 +156,21 @@ contains
|
|||
end if
|
||||
end if
|
||||
end select
|
||||
|
||||
! Check for rejection
|
||||
if (.not. found) then
|
||||
n_reject = n_reject + 1
|
||||
if (n_reject >= EXTSRC_REJECT_THRESHOLD .and. &
|
||||
real(n_accept, 8)/n_reject <= EXTSRC_REJECT_FRACTION) then
|
||||
call fatal_error("More than 95% of external source sites sampled &
|
||||
&were rejected. Please check your external source definition.")
|
||||
end if
|
||||
end if
|
||||
end do
|
||||
|
||||
! Increment number of accepted samples
|
||||
n_accept = n_accept + 1
|
||||
|
||||
call p % clear()
|
||||
|
||||
! Sample angle
|
||||
|
|
|
|||
|
|
@ -29,39 +29,39 @@
|
|||
1 10000 1 total 0.385188 0.026946
|
||||
0 10000 2 total 0.412389 0.015425
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10000 1 1 total P0 -0.000207 0.000149
|
||||
11 10000 1 1 total P1 0.000234 0.000128
|
||||
13 10000 1 1 total P2 0.051870 0.006983
|
||||
12 10000 1 1 total P0 0.384199 0.027001
|
||||
13 10000 1 1 total P1 0.051870 0.006983
|
||||
14 10000 1 1 total P2 0.020069 0.002846
|
||||
15 10000 1 1 total P3 0.009478 0.002234
|
||||
8 10000 1 2 total P0 0.000989 0.000482
|
||||
10 10000 1 2 total P1 -0.000103 0.000184
|
||||
12 10000 1 2 total P2 0.384199 0.027001
|
||||
14 10000 1 2 total P3 0.020069 0.002846
|
||||
1 10000 2 1 total P0 0.016482 0.004502
|
||||
3 10000 2 1 total P1 -0.010499 0.010438
|
||||
5 10000 2 1 total P2 -0.000768 0.000768
|
||||
9 10000 1 2 total P1 -0.000207 0.000149
|
||||
10 10000 1 2 total P2 -0.000103 0.000184
|
||||
11 10000 1 2 total P3 0.000234 0.000128
|
||||
4 10000 2 1 total P0 0.000925 0.000925
|
||||
5 10000 2 1 total P1 -0.000768 0.000768
|
||||
6 10000 2 1 total P2 0.000494 0.000494
|
||||
7 10000 2 1 total P3 -0.000171 0.000172
|
||||
0 10000 2 2 total P0 0.411465 0.015245
|
||||
2 10000 2 2 total P1 0.006371 0.010551
|
||||
4 10000 2 2 total P2 0.000925 0.000925
|
||||
6 10000 2 2 total P3 0.000494 0.000494
|
||||
1 10000 2 2 total P1 0.016482 0.004502
|
||||
2 10000 2 2 total P2 0.006371 0.010551
|
||||
3 10000 2 2 total P3 -0.010499 0.010438
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10000 1 1 total P0 -0.000207 0.000149
|
||||
11 10000 1 1 total P1 0.000234 0.000128
|
||||
13 10000 1 1 total P2 0.051870 0.006983
|
||||
12 10000 1 1 total P0 0.384199 0.027001
|
||||
13 10000 1 1 total P1 0.051870 0.006983
|
||||
14 10000 1 1 total P2 0.020069 0.002846
|
||||
15 10000 1 1 total P3 0.009478 0.002234
|
||||
8 10000 1 2 total P0 0.000989 0.000482
|
||||
10 10000 1 2 total P1 -0.000103 0.000184
|
||||
12 10000 1 2 total P2 0.384199 0.027001
|
||||
14 10000 1 2 total P3 0.020069 0.002846
|
||||
1 10000 2 1 total P0 0.016482 0.004502
|
||||
3 10000 2 1 total P1 -0.010499 0.010438
|
||||
5 10000 2 1 total P2 -0.000768 0.000768
|
||||
9 10000 1 2 total P1 -0.000207 0.000149
|
||||
10 10000 1 2 total P2 -0.000103 0.000184
|
||||
11 10000 1 2 total P3 0.000234 0.000128
|
||||
4 10000 2 1 total P0 0.000925 0.000925
|
||||
5 10000 2 1 total P1 -0.000768 0.000768
|
||||
6 10000 2 1 total P2 0.000494 0.000494
|
||||
7 10000 2 1 total P3 -0.000171 0.000172
|
||||
0 10000 2 2 total P0 0.411465 0.015245
|
||||
2 10000 2 2 total P1 0.006371 0.010551
|
||||
4 10000 2 2 total P2 0.000925 0.000925
|
||||
6 10000 2 2 total P3 0.000494 0.000494
|
||||
1 10000 2 2 total P1 0.016482 0.004502
|
||||
2 10000 2 2 total P2 0.006371 0.010551
|
||||
3 10000 2 2 total P3 -0.010499 0.010438
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10000 1 1 total 1.0 0.078516
|
||||
2 10000 1 2 total 1.0 0.687184
|
||||
|
|
@ -154,39 +154,39 @@
|
|||
1 10001 1 total 0.310121 0.033788
|
||||
0 10001 2 total 0.296264 0.043792
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10001 1 1 total P0 0.000000 0.000000
|
||||
11 10001 1 1 total P1 0.000000 0.000000
|
||||
13 10001 1 1 total P2 0.038230 0.008484
|
||||
12 10001 1 1 total P0 0.310121 0.033788
|
||||
13 10001 1 1 total P1 0.038230 0.008484
|
||||
14 10001 1 1 total P2 0.020745 0.004696
|
||||
15 10001 1 1 total P3 0.007964 0.003732
|
||||
8 10001 1 2 total P0 0.000000 0.000000
|
||||
10 10001 1 2 total P1 0.000000 0.000000
|
||||
12 10001 1 2 total P2 0.310121 0.033788
|
||||
14 10001 1 2 total P3 0.020745 0.004696
|
||||
1 10001 2 1 total P0 -0.011214 0.016180
|
||||
3 10001 2 1 total P1 -0.003270 0.007329
|
||||
5 10001 2 1 total P2 0.000000 0.000000
|
||||
9 10001 1 2 total P1 0.000000 0.000000
|
||||
10 10001 1 2 total P2 0.000000 0.000000
|
||||
11 10001 1 2 total P3 0.000000 0.000000
|
||||
4 10001 2 1 total P0 0.000000 0.000000
|
||||
5 10001 2 1 total P1 0.000000 0.000000
|
||||
6 10001 2 1 total P2 0.000000 0.000000
|
||||
7 10001 2 1 total P3 0.000000 0.000000
|
||||
0 10001 2 2 total P0 0.296264 0.043792
|
||||
2 10001 2 2 total P1 0.008837 0.011504
|
||||
4 10001 2 2 total P2 0.000000 0.000000
|
||||
6 10001 2 2 total P3 0.000000 0.000000
|
||||
1 10001 2 2 total P1 -0.011214 0.016180
|
||||
2 10001 2 2 total P2 0.008837 0.011504
|
||||
3 10001 2 2 total P3 -0.003270 0.007329
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10001 1 1 total P0 0.000000 0.000000
|
||||
11 10001 1 1 total P1 0.000000 0.000000
|
||||
13 10001 1 1 total P2 0.038230 0.008484
|
||||
12 10001 1 1 total P0 0.310121 0.033788
|
||||
13 10001 1 1 total P1 0.038230 0.008484
|
||||
14 10001 1 1 total P2 0.020745 0.004696
|
||||
15 10001 1 1 total P3 0.007964 0.003732
|
||||
8 10001 1 2 total P0 0.000000 0.000000
|
||||
10 10001 1 2 total P1 0.000000 0.000000
|
||||
12 10001 1 2 total P2 0.310121 0.033788
|
||||
14 10001 1 2 total P3 0.020745 0.004696
|
||||
1 10001 2 1 total P0 -0.011214 0.016180
|
||||
3 10001 2 1 total P1 -0.003270 0.007329
|
||||
5 10001 2 1 total P2 0.000000 0.000000
|
||||
9 10001 1 2 total P1 0.000000 0.000000
|
||||
10 10001 1 2 total P2 0.000000 0.000000
|
||||
11 10001 1 2 total P3 0.000000 0.000000
|
||||
4 10001 2 1 total P0 0.000000 0.000000
|
||||
5 10001 2 1 total P1 0.000000 0.000000
|
||||
6 10001 2 1 total P2 0.000000 0.000000
|
||||
7 10001 2 1 total P3 0.000000 0.000000
|
||||
0 10001 2 2 total P0 0.296264 0.043792
|
||||
2 10001 2 2 total P1 0.008837 0.011504
|
||||
4 10001 2 2 total P2 0.000000 0.000000
|
||||
6 10001 2 2 total P3 0.000000 0.000000
|
||||
1 10001 2 2 total P1 -0.011214 0.016180
|
||||
2 10001 2 2 total P2 0.008837 0.011504
|
||||
3 10001 2 2 total P3 -0.003270 0.007329
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10001 1 1 total 1.0 0.108779
|
||||
2 10001 1 2 total 0.0 0.000000
|
||||
|
|
@ -279,39 +279,39 @@
|
|||
1 10002 1 total 0.671269 0.026186
|
||||
0 10002 2 total 2.035388 0.258060
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10002 1 1 total P0 0.008758 0.000926
|
||||
11 10002 1 1 total P1 -0.003785 0.000817
|
||||
13 10002 1 1 total P2 0.381167 0.016243
|
||||
12 10002 1 1 total P0 0.639901 0.024709
|
||||
13 10002 1 1 total P1 0.381167 0.016243
|
||||
14 10002 1 1 total P2 0.152392 0.008156
|
||||
15 10002 1 1 total P3 0.009148 0.003889
|
||||
8 10002 1 2 total P0 0.031368 0.001728
|
||||
10 10002 1 2 total P1 -0.002568 0.001014
|
||||
12 10002 1 2 total P2 0.639901 0.024709
|
||||
14 10002 1 2 total P3 0.152392 0.008156
|
||||
1 10002 2 1 total P0 0.509941 0.051236
|
||||
3 10002 2 1 total P1 0.024988 0.008312
|
||||
5 10002 2 1 total P2 0.000400 0.000401
|
||||
9 10002 1 2 total P1 0.008758 0.000926
|
||||
10 10002 1 2 total P2 -0.002568 0.001014
|
||||
11 10002 1 2 total P3 -0.003785 0.000817
|
||||
4 10002 2 1 total P0 0.000443 0.000445
|
||||
5 10002 2 1 total P1 0.000400 0.000401
|
||||
6 10002 2 1 total P2 0.000320 0.000321
|
||||
7 10002 2 1 total P3 0.000214 0.000215
|
||||
0 10002 2 2 total P0 2.034945 0.257800
|
||||
2 10002 2 2 total P1 0.111175 0.013020
|
||||
4 10002 2 2 total P2 0.000443 0.000445
|
||||
6 10002 2 2 total P3 0.000320 0.000321
|
||||
1 10002 2 2 total P1 0.509941 0.051236
|
||||
2 10002 2 2 total P2 0.111175 0.013020
|
||||
3 10002 2 2 total P3 0.024988 0.008312
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
9 10002 1 1 total P0 0.008758 0.000926
|
||||
11 10002 1 1 total P1 -0.003785 0.000817
|
||||
13 10002 1 1 total P2 0.381167 0.016243
|
||||
12 10002 1 1 total P0 0.639901 0.024709
|
||||
13 10002 1 1 total P1 0.381167 0.016243
|
||||
14 10002 1 1 total P2 0.152392 0.008156
|
||||
15 10002 1 1 total P3 0.009148 0.003889
|
||||
8 10002 1 2 total P0 0.031368 0.001728
|
||||
10 10002 1 2 total P1 -0.002568 0.001014
|
||||
12 10002 1 2 total P2 0.639901 0.024709
|
||||
14 10002 1 2 total P3 0.152392 0.008156
|
||||
1 10002 2 1 total P0 0.509941 0.051236
|
||||
3 10002 2 1 total P1 0.024988 0.008312
|
||||
5 10002 2 1 total P2 0.000400 0.000401
|
||||
9 10002 1 2 total P1 0.008758 0.000926
|
||||
10 10002 1 2 total P2 -0.002568 0.001014
|
||||
11 10002 1 2 total P3 -0.003785 0.000817
|
||||
4 10002 2 1 total P0 0.000443 0.000445
|
||||
5 10002 2 1 total P1 0.000400 0.000401
|
||||
6 10002 2 1 total P2 0.000320 0.000321
|
||||
7 10002 2 1 total P3 0.000214 0.000215
|
||||
0 10002 2 2 total P0 2.034945 0.257800
|
||||
2 10002 2 2 total P1 0.111175 0.013020
|
||||
4 10002 2 2 total P2 0.000443 0.000445
|
||||
6 10002 2 2 total P3 0.000320 0.000321
|
||||
1 10002 2 2 total P1 0.509941 0.051236
|
||||
2 10002 2 2 total P2 0.111175 0.013020
|
||||
3 10002 2 2 total P3 0.024988 0.008312
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10002 1 1 total 1.0 0.038609
|
||||
2 10002 1 2 total 1.0 0.067667
|
||||
|
|
|
|||
|
|
@ -1 +1 @@
|
|||
8142ae4e107002a835999e4ace85c17376f262a7059fc224f3756a2de19aba6ca4c4fa14ca2085c87d7729aa8d6d6f78fdae21ac6dfe33ca303449c769076074
|
||||
e494320a213b5704a2ac915a2ba504857be91961ceb6735b6ad05d81eb31c44c9584d5bd9d40baececf1dcb5b030e6ecec63cfbd20639baf69bcb596c5c46591
|
||||
Loading…
Add table
Add a link
Reference in a new issue