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Simply MeshFilter.__init__

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Sterling Harper 2016-09-30 00:01:10 -04:00
parent e464e22690
commit 52c9898128
19 changed files with 209 additions and 183 deletions
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docs/source/pythonapi/examples/mdgxs-part-ii.ipynb
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docs/source/pythonapi/examples/mgxs-part-iii.ipynb
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docs/source/pythonapi/examples/tally-arithmetic.ipynb
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@ -338,7 +338,7 @@
"outputs": [
{
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"text/plain": [
"<IPython.core.display.Image object>"
]
@ -417,8 +417,7 @@
"mesh.dimension = [1, 1, 1]\n",
"mesh.lower_left = [-0.63, -0.63, -100.]\n",
"mesh.width = [1.26, 1.26, 200.]\n",
"mesh_filter = openmc.MeshFilter(mesh.id)\n",
"mesh_filter.mesh = mesh\n",
"mesh_filter = openmc.MeshFilter(mesh)\n",
"\n",
"# Instantiate thermal, fast, and total leakage tallies\n",
"leak = openmc.Tally(name='leakage')\n",
@ -579,8 +578,8 @@
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
" Version | 0.8.0\n",
" Git SHA1 | 57371d217a270b4013af4e33ca20b0053654b190\n",
" Date/Time | 2016-09-21 16:42:14\n",
" Git SHA1 | b02fa21928a37a2254bec13c9802ff8173b6aefd\n",
" Date/Time | 2016-09-29 23:59:21\n",
" MPI Processes | 1\n",
"\n",
" ===========================================================================\n",
@ -637,20 +636,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 2.8800E-01 seconds\n",
" Reading cross sections = 1.6900E-01 seconds\n",
" Total time in simulation = 1.5410E+01 seconds\n",
" Time in transport only = 1.5395E+01 seconds\n",
" Time in inactive batches = 2.3750E+00 seconds\n",
" Time in active batches = 1.3035E+01 seconds\n",
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
" Sampling source sites = 2.0000E-03 seconds\n",
" SEND/RECV source sites = 2.0000E-03 seconds\n",
" Time accumulating tallies = 1.0000E-03 seconds\n",
" Total time for finalization = 3.0000E-03 seconds\n",
" Total time elapsed = 1.5718E+01 seconds\n",
" Calculation Rate (inactive) = 5263.16 neutrons/second\n",
" Calculation Rate (active) = 2876.87 neutrons/second\n",
" Total time for initialization = 2.9900E-01 seconds\n",
" Reading cross sections = 1.8000E-01 seconds\n",
" Total time in simulation = 1.6156E+01 seconds\n",
" Time in transport only = 1.6145E+01 seconds\n",
" Time in inactive batches = 2.3940E+00 seconds\n",
" Time in active batches = 1.3762E+01 seconds\n",
" Time synchronizing fission bank = 1.0000E-03 seconds\n",
" Sampling source sites = 1.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 1.6476E+01 seconds\n",
" Calculation Rate (inactive) = 5221.39 neutrons/second\n",
" Calculation Rate (active) = 2724.89 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",

3
examples/python/lattice/nested/build-xml.py
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@ -162,8 +162,7 @@ mesh.lower_left = [-2, -2]
mesh.width = [1, 1]
# Instantiate tally Filter
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate the Tally
tally = openmc.Tally(tally_id=1)

3
examples/python/lattice/simple/build-xml.py
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@ -155,8 +155,7 @@ mesh.lower_left = [-2, -2]
mesh.width = [1, 1]
# Instantiate tally Filter
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate tally Trigger
trigger = openmc.Trigger(trigger_type='rel_err', threshold=1E-2)

3
examples/python/pincell/build-xml.py
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@ -186,8 +186,7 @@ mesh.upper_right = [0.62992, 0.62992, 1.e50]
# Instantiate some tally Filters
energy_filter = openmc.EnergyFilter([0., 4.e-6, 20.])
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate the Tally
tally = openmc.Tally(tally_id=1, name='tally 1')

3
examples/python/pincell_multigroup/build-xml.py
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@ -155,8 +155,7 @@ mesh.upper_right = [0.63, 0.63, 1.e50]
# Instantiate some tally Filters
energy_filter = openmc.EnergyFilter([1E-11, 0.0635E-6, 10.0E-6, 1.0E-4, 1.0E-3,
0.5, 1.0, 20.0])
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate the Tally
tally = openmc.Tally(tally_id=1, name='tally 1')

63
openmc/filter.py
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@ -38,7 +38,7 @@ class FilterMeta(ABCMeta):
class Filter(with_metaclass(FilterMeta, object)):
"""A constraint on transport events that can score a tally.
"""Tally modifier that describes phase-space and other characteristics.
Parameters
----------
@ -107,7 +107,7 @@ class Filter(with_metaclass(FilterMeta, object)):
return subs + subsubs
@classmethod
def from_hdf5(cls, group):
def from_hdf5(cls, group, **kwargs):
"""Construct a new Filter instance from HDF5 data.
Parameters
@ -115,16 +115,26 @@ class Filter(with_metaclass(FilterMeta, object)):
group : h5py.Group
HDF5 group to read from
Keyword arguments
-----------------
meshes : dict
Dictionary mapping integer IDs to openmc.Mesh objects. Only used
for openmc.MeshFilter objects.
"""
# If the HDF5 'type' variable matches this class's short_name, then
# there is no overriden from_hdf5 method. Pass the bins to __init__.
if group['type'].value.decode() == cls.short_name.lower():
out = cls(group['bins'].value)
out.num_bins = group['n_bins'].value
return out
# Search through all subclasses and find the one matching the HDF5
# 'type'. Call that class's from_hdf5 method.
for subclass in cls.recursive_subclasses():
if group['type'].value.decode() == subclass.short_name.lower():
return subclass.from_hdf5(group)
return subclass.from_hdf5(group, **kwargs)
raise ValueError("Unrecognized Filter class: '"
+ group['type'].value.decode() + "'")
@ -447,9 +457,48 @@ class SurfaceFilter(IntegralFilter):
class MeshFilter(Filter):
def __init__(self, bins):
self._mesh = None
super(MeshFilter, self).__init__(bins)
"""Bins tally event locations onto a regular, rectangular mesh.
Parameters
----------
mesh : openmc.Mesh
The Mesh object that events will be tallied onto
Attributes
----------
bins : Integral
The Mesh ID
mesh : openmc.Mesh
The Mesh object that events will be tallied onto
num_bins : Integral
The number of filter bins
stride : Integral
The number of filter, nuclide and score bins within each of this
filter's bins.
"""
def __init__(self, mesh):
self.mesh = mesh
super(MeshFilter, self).__init__(mesh.id)
@classmethod
def from_hdf5(cls, group, **kwargs):
if group['type'].value.decode() != cls.short_name.lower():
raise ValueError("Expected HDF5 data for filter type '"
+ cls.short_name.lower() + "' but got '"
+ group['type'].value.decode() + " instead")
if not 'meshes' in kwargs:
raise ValueError(cls.__name__ + " requires a 'meshes' keyword "
"argument.")
mesh_id = group['bins'].value
mesh_obj = kwargs['meshes'][mesh_id]
out = cls(mesh_obj)
out.num_bins = group['n_bins'].value
return out
@property
def mesh(self):
@ -706,7 +755,7 @@ class DistribcellFilter(Filter):
super(DistribcellFilter, self).__init__(bins)
@classmethod
def from_hdf5(cls, group):
def from_hdf5(cls, group, **kwargs):
if group['type'].value.decode() != cls.short_name.lower():
raise ValueError("Expected HDF5 data for filter type '"
+ cls.short_name.lower() + "' but got '"

7
openmc/mgxs/mgxs.py
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@ -271,11 +271,10 @@ class MGXS(object):
# Create a domain Filter object
filter_type = _DOMAIN_TO_FILTER[self.domain_type]
domain_filter = filter_type(self.domain.id)
# If a mesh domain, give the mesh to the domain filter
if self.domain_type == 'mesh':
domain_filter.mesh = self.domain
domain_filter = filter_type(self.domain)
else:
domain_filter = filter_type(self.domain.id)
# Create each Tally needed to compute the multi group cross section
tally_metadata = zip(self.scores, self.tally_keys, self.filters)

8
openmc/statepoint.py
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@ -408,12 +408,8 @@ class StatePoint(object):
# Read all filters
for j in range(1, n_filters+1):
subsubbase = '{0}{1}'.format(subbase, j)
new_filter = openmc.Filter.from_hdf5(self._f[subsubbase])
if isinstance(new_filter, openmc.MeshFilter):
mesh_ids = self._f['tallies/meshes/ids'].value
mesh_keys = self._f['tallies/meshes/keys'].value
key = mesh_keys[mesh_ids == new_filter.bins[0]][0]
new_filter.mesh = self.meshes[key]
new_filter = openmc.Filter.from_hdf5(self._f[subsubbase],
meshes=self.meshes)
tally.filters.append(new_filter)
# Read Nuclide bins

2
src/tally_filter.F90
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@ -418,7 +418,7 @@ contains
call write_dataset(filter_group, "type", "mesh")
call write_dataset(filter_group, "n_bins", this % n_bins)
call write_dataset(filter_group, "bins", this % mesh )
call write_dataset(filter_group, "bins", meshes(this % mesh) % id)
end subroutine to_statepoint_mesh
function text_label_mesh(this, bin) result(label)

9
tests/test_filter_mesh/test_filter_mesh.py
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@ -38,12 +38,9 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
mesh_3d.upper_right = [182.07, 182.07, 183.00]
# Initialize the filters
mesh_1d_filter = openmc.MeshFilter(mesh_1d.id)
mesh_2d_filter = openmc.MeshFilter(mesh_2d.id)
mesh_3d_filter = openmc.MeshFilter(mesh_3d.id)
mesh_1d_filter.mesh = mesh_1d
mesh_2d_filter.mesh = mesh_2d
mesh_3d_filter.mesh = mesh_3d
mesh_1d_filter = openmc.MeshFilter(mesh_1d)
mesh_2d_filter = openmc.MeshFilter(mesh_2d)
mesh_3d_filter = openmc.MeshFilter(mesh_3d)
# Initialized the tallies
tally = openmc.Tally(name='tally 1')

3
tests/test_mg_tallies/test_mg_tallies.py
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@ -19,8 +19,7 @@ class MGTalliesTestHarness(PyAPITestHarness):
# Instantiate some tally filters
energy_filter = openmc.EnergyFilter([0.0, 20.0])
energyout_filter = openmc.EnergyoutFilter([0.0, 20.0])
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
mat_filter = openmc.MaterialFilter([1,2,3])

3
tests/test_tallies/test_tallies.py
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@ -43,8 +43,7 @@ class TalliesTestHarness(PyAPITestHarness):
mesh_2x2.lower_left = [-182.07, -182.07]
mesh_2x2.upper_right = [182.07, 182.07]
mesh_2x2.dimension = [2, 2]
mesh_filter = MeshFilter(mesh_2x2.id)
mesh_filter.mesh = mesh_2x2
mesh_filter = MeshFilter(mesh_2x2)
azimuthal_tally4 = Tally()
azimuthal_tally4.filters = [azimuthal_filter2, mesh_filter]
azimuthal_tally4.scores = ['flux']

3
tests/test_tally_arithmetic/test_tally_arithmetic.py
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@ -34,8 +34,7 @@ class TallyArithmeticTestHarness(PyAPITestHarness):
energy_filter = openmc.EnergyFilter((0.0, 0.253e-6, 1.0e-3, 1.0, 20.0))
material_filter = openmc.MaterialFilter((1, 3))
distrib_filter = openmc.DistribcellFilter(60)
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
# Initialized the tallies
tally = openmc.Tally(name='tally 1')

3
tests/test_tally_slice_merge/test_tally_slice_merge.py
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@ -40,8 +40,7 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
mesh.dimension = [2, 2]
mesh.lower_left = [-50., -50.]
mesh.upper_right = [+50., +50.]
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
mesh_filter = openmc.MeshFilter(mesh)
self.cell_filters = [cell_21, cell_27]
self.energy_filters = [low_energy, high_energy]