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Continue adding docstrings and updating modules.

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This commit is contained in:
Paul Romano 2015-06-02 19:22:33 +07:00
parent 7ed1dd17e6
commit c8e176a9f7
17 changed files with 760 additions and 635 deletions
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48
openmc/summary.py
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@ -10,9 +10,12 @@ except ImportError:
class Summary(object):
"""Information summarizing the geometry, materials, and tallies used in a
simulation.
"""
def __init__(self, filename):
openmc.reset_auto_ids()
if not filename.endswith(('.h5', '.hdf5')):
@ -27,9 +30,7 @@ class Summary(object):
self._read_geometry()
self._read_tallies()
def _read_metadata(self):
# Read OpenMC version
self.version = [self._f['version_major'][0],
self._f['version_minor'][0],
@ -44,9 +45,7 @@ class Summary(object):
self.gen_per_batch = self._f['gen_per_batch'][0]
self.n_procs = self._f['n_procs'][0]
def _read_geometry(self):
# Read in and initialize the Materials and Geometry
self._read_nuclides()
self._read_materials()
@ -56,9 +55,7 @@ class Summary(object):
self._read_lattices()
self._finalize_geometry()
def _read_nuclides(self):
self.n_nuclides = self._f['nuclides/n_nuclides'][0]
# Initialize dictionary for each Nuclide
@ -67,7 +64,6 @@ class Summary(object):
self.nuclides = {}
for key in self._f['nuclides'].keys():
if key == 'n_nuclides':
continue
@ -88,9 +84,7 @@ class Summary(object):
self.nuclides[zaid] = openmc.Nuclide(name=name, xs=xs)
self.nuclides[zaid].zaid = zaid
def _read_materials(self):
self.n_materials = self._f['materials/n_materials'][0]
# Initialize dictionary for each Material
@ -99,7 +93,6 @@ class Summary(object):
self.materials = {}
for key in self._f['materials'].keys():
if key == 'n_materials':
continue
@ -116,7 +109,6 @@ class Summary(object):
# Read the names of the S(a,b) tables for this Material
for i in range(1, n_sab+1):
sab_table = self._f['materials'][key]['sab_tables'][str(i)][0]
# Read the cross-section identifiers for each S(a,b) table
@ -148,9 +140,7 @@ class Summary(object):
# Add the Material to the global dictionary of all Materials
self.materials[index] = material
def _read_surfaces(self):
self.n_surfaces = self._f['geometry/n_surfaces'][0]
# Initialize dictionary for each Surface
@ -159,7 +149,6 @@ class Summary(object):
self.surfaces = {}
for key in self._f['geometry/surfaces'].keys():
if key == 'n_surfaces':
continue
@ -171,7 +160,6 @@ class Summary(object):
coeffs = self._f['geometry/surfaces'][key]['coefficients'][...]
# Create the Surface based on its type
if surf_type == 'X Plane':
x0 = coeffs[0]
surface = openmc.XPlane(surface_id, bc, x0, name)
@ -232,9 +220,7 @@ class Summary(object):
# Add Surface to global dictionary of all Surfaces
self.surfaces[index] = surface
def _read_cells(self):
self.n_cells = self._f['geometry/n_cells'][0]
# Initialize dictionary for each Cell
@ -251,7 +237,6 @@ class Summary(object):
self._cell_fills = {}
for key in self._f['geometry/cells'].keys():
if key == 'n_cells':
continue
@ -310,9 +295,7 @@ class Summary(object):
# Add the Cell to the global dictionary of all Cells
self.cells[index] = cell
def _read_universes(self):
self.n_universes = self._f['geometry/n_universes'][0]
# Initialize dictionary for each Universe
@ -321,7 +304,6 @@ class Summary(object):
self.universes = {}
for key in self._f['geometry/universes'].keys():
if key == 'n_universes':
continue
@ -340,9 +322,7 @@ class Summary(object):
# Add the Universe to the global list of Universes
self.universes[index] = universe
def _read_lattices(self):
self.n_lattices = self._f['geometry/n_lattices'][0]
# Initialize lattices for each Lattice
@ -351,7 +331,6 @@ class Summary(object):
self.lattices = {}
for key in self._f['geometry/lattices'].keys():
if key == 'n_lattices':
continue
@ -451,15 +430,12 @@ class Summary(object):
# Add the Lattice to the global dictionary of all Lattices
self.lattices[index] = lattice
def _finalize_geometry(self):
# Initialize Geometry object
self.openmc_geometry = openmc.Geometry()
# Iterate over all Cells and add fill Materials, Universes and Lattices
for cell_key in self._cell_fills.keys():
# Determine fill type ('normal', 'universe', or 'lattice') and ID
fill_type = self._cell_fills[cell_key][0]
fill_id = self._cell_fills[cell_key][1]
@ -482,9 +458,7 @@ class Summary(object):
root_universe = self.get_universe_by_id(0)
self.openmc_geometry.root_universe = root_universe
def _read_tallies(self):
# Initialize dictionaries for the Tallies
# Keys - Tally IDs
# Values - Tally objects
@ -554,9 +528,7 @@ class Summary(object):
# Add Tally to the global dictionary of all Tallies
self.tallies[tally_id] = tally
def make_opencg_geometry(self):
try:
from openmc.opencg_compatible import get_opencg_geometry
except ImportError:
@ -567,54 +539,42 @@ class Summary(object):
if self.opencg_geometry is None:
self.opencg_geometry = get_opencg_geometry(self.openmc_geometry)
def get_nuclide_by_zaid(self, zaid):
for index, nuclide in self.nuclides.items():
if nuclide._zaid == zaid:
return nuclide
return None
def get_material_by_id(self, material_id):
for index, material in self.materials.items():
if material._id == material_id:
return material
return None
def get_surface_by_id(self, surface_id):
for index, surface in self.surfaces.items():
if surface._id == surface_id:
return surface
return None
def get_cell_by_id(self, cell_id):
for index, cell in self.cells.items():
if cell._id == cell_id:
return cell
return None
def get_universe_by_id(self, universe_id):
for index, universe in self.universes.items():
if universe._id == universe_id:
return universe
return None
def get_lattice_by_id(self, lattice_id):
for index, lattice in self.lattices.items():
if lattice._id == lattice_id:
return lattice