More docstrings and updates

This commit is contained in:
Paul Romano 2015-06-13 17:21:41 +07:00
parent c8e176a9f7
commit 2eb129fc67
5 changed files with 829 additions and 312 deletions

View file

@ -975,6 +975,19 @@ def get_openmc_lattice(opencg_lattice):
def get_opencg_geometry(openmc_geometry):
"""Return an OpenCG geometry corresponding to an OpenMC geometry.
Parameters
----------
openmc_geometry : openmc.universe.Geometry
OpenMC geometry
Returns
-------
opencg_geometry : opencg.Geometry
Equivalent OpenCG geometry
"""
if not isinstance(openmc_geometry, openmc.Geometry):
msg = 'Unable to get OpenCG geometry from {0} which is ' \

View file

@ -522,7 +522,8 @@ class StatePoint(object):
sum_sq = np.reshape(sum_sq, new_shape)
# Set the data for this Tally
tally.set_results(sum=sum, sum_sq=sum_sq)
tally.sum = sum
tally.sum_sq = sum_sq
# Indicate that Tally results have been read
self._results = True

View file

@ -529,6 +529,11 @@ class Summary(object):
self.tallies[tally_id] = tally
def make_opencg_geometry(self):
"""Create OpenCG geometry based on the information contained in the summary
file. The geometry is stored as the 'opencg_geometry' attribute.
"""
try:
from openmc.opencg_compatible import get_opencg_geometry
except ImportError:
@ -540,6 +545,22 @@ class Summary(object):
self.opencg_geometry = get_opencg_geometry(self.openmc_geometry)
def get_nuclide_by_zaid(self, zaid):
"""Return a Nuclide object given the 'zaid' identifier for the nuclide.
Parameters
----------
zaid : int
1000*Z + A, where Z is the atomic number of the nuclide and A is the
mass number. For example, the zaid for U-235 is 92235.
Returns
-------
nuclide : openmc.nuclide.Nuclide
Nuclide matching the specified zaid
"""
for index, nuclide in self.nuclides.items():
if nuclide._zaid == zaid:
return nuclide
@ -547,6 +568,20 @@ class Summary(object):
return None
def get_material_by_id(self, material_id):
"""Return a Material object given the material id
Parameters
----------
id : int
Unique identifier for the material
Returns
-------
material : openmc.material.Material
Material with given id
"""
for index, material in self.materials.items():
if material._id == material_id:
return material
@ -554,6 +589,20 @@ class Summary(object):
return None
def get_surface_by_id(self, surface_id):
"""Return a Surface object given the surface id
Parameters
----------
id : int
Unique identifier for the surface
Returns
-------
surface : openmc.surface.Surface
Surface with given id
"""
for index, surface in self.surfaces.items():
if surface._id == surface_id:
return surface
@ -561,6 +610,20 @@ class Summary(object):
return None
def get_cell_by_id(self, cell_id):
"""Return a Cell object given the cell id
Parameters
----------
id : int
Unique identifier for the cell
Returns
-------
cell : openmc.universe.Cell
Cell with given id
"""
for index, cell in self.cells.items():
if cell._id == cell_id:
return cell
@ -568,6 +631,20 @@ class Summary(object):
return None
def get_universe_by_id(self, universe_id):
"""Return a Universe object given the universe id
Parameters
----------
id : int
Unique identifier for the universe
Returns
-------
universe : openmc.universe.Universe
Universe with given id
"""
for index, universe in self.universes.items():
if universe._id == universe_id:
return universe
@ -575,6 +652,20 @@ class Summary(object):
return None
def get_lattice_by_id(self, lattice_id):
"""Return a Lattice object given the lattice id
Parameters
----------
id : int
Unique identifier for the lattice
Returns
-------
lattice : openmc.universe.Lattice
Lattice with given id
"""
for index, lattice in self.lattices.items():
if lattice._id == lattice_id:
return lattice

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