def _create_geometry(self):
"""Instantiate materials and a pin cell Geometry."""
self.input_set.create_materials()
zcylinder = openmoc.ZCylinder(x=0.0, y=0.0, radius=1.0, name='pin')
xmin = openmoc.XPlane(x=-2.0, name='xmin')
xmax = openmoc.XPlane(x=+2.0, name='xmax')
ymin = openmoc.YPlane(y=-2.0, name='ymin')
ymax = openmoc.YPlane(y=+2.0, name='ymax')
xmin.setBoundaryType(openmoc.VACUUM)
xmax.setBoundaryType(openmoc.VACUUM)
ymin.setBoundaryType(openmoc.VACUUM)
ymax.setBoundaryType(openmoc.VACUUM)
fuel = openmoc.Cell(name='fuel')
fuel.setFill(self.input_set.materials['UO2'])
fuel.addSurface(halfspace=-1, surface=zcylinder)
moderator = openmoc.Cell(name='moderator')
moderator.setFill(self.input_set.materials['Water'])
moderator.addSurface(halfspace=+1, surface=zcylinder)
moderator.addSurface(halfspace=+1, surface=xmin)
moderator.addSurface(halfspace=-1, surface=xmax)
moderator.addSurface(halfspace=+1, surface=ymin)
moderator.addSurface(halfspace=-1, surface=ymax)
root_universe = openmoc.Universe(name='root universe')
root_universe.addCell(fuel)
root_universe.addCell(moderator)
self.input_set.geometry = openmoc.Geometry()
self.input_set.geometry.setRootUniverse(root_universe)
def get_openmoc_geometry(openmc_geometry):
"""Return an OpenMC geometry corresponding to an OpenMOC geometry.
Parameters
----------
openmc_geometry : openmc.Geometry
OpenMC geometry
Returns
-------
openmoc_geometry : openmoc.Geometry
Equivalent OpenMOC geometry
"""
cv.check_type('openmc_geometry', openmc_geometry, openmc.Geometry)
# Clear dictionaries and auto-generated IDs
OPENMC_SURFACES.clear()
OPENMOC_SURFACES.clear()
OPENMC_CELLS.clear()
OPENMOC_CELLS.clear()
OPENMC_UNIVERSES.clear()
OPENMOC_UNIVERSES.clear()
OPENMC_LATTICES.clear()
OPENMOC_LATTICES.clear()
openmc_root_universe = openmc_geometry.root_universe
openmoc_root_universe = get_openmoc_universe(openmc_root_universe)
openmoc_geometry = openmoc.Geometry()
openmoc_geometry.setRootUniverse(openmoc_root_universe)
# Update OpenMOC's auto-generated object IDs (e.g., Surface, Material)
# with the maximum of those created from the OpenMC objects
all_materials = openmoc_geometry.getAllMaterials()
all_surfaces = openmoc_geometry.getAllSurfaces()
all_cells = openmoc_geometry.getAllCells()
all_universes = openmoc_geometry.getAllUniverses()
max_material_id = max(all_materials.keys())
max_surface_id = max(all_surfaces.keys())
max_cell_id = max(all_cells.keys())
max_universe_id = max(all_universes.keys())
openmoc.maximize_material_id(max_material_id+1)
openmoc.maximize_surface_id(max_surface_id+1)
openmoc.maximize_cell_id(max_cell_id+1)
openmoc.maximize_universe_id(max_universe_id+1)
return openmoc_geometry
def create_geometry(self):
"""Instantiate a 3x2 grid Geometry by making a lattice"""
# Create the planes bounding the geometry
xmin = openmoc.XPlane(x=-3.0, name='xmin')
xmax = openmoc.XPlane(x=3.0, name='xmax')
ymin = openmoc.YPlane(y=-2.0, name='ymin')
ymax = openmoc.YPlane(y=2.0, name='ymax')
xmin.setBoundaryType(openmoc.REFLECTIVE)
xmax.setBoundaryType(openmoc.REFLECTIVE)
ymin.setBoundaryType(openmoc.REFLECTIVE)
ymax.setBoundaryType(openmoc.REFLECTIVE)
# Create the root cell, bounded by the geometry bounds
root_cell = openmoc.Cell(name='root cell')
root_cell.addSurface(halfspace=+1, surface=xmin)
root_cell.addSurface(halfspace=-1, surface=xmax)
root_cell.addSurface(halfspace=+1, surface=ymin)
root_cell.addSurface(halfspace=-1, surface=ymax)
# Create UO2, water, and tube cells
uo2_cell = openmoc.Cell(name='UO2 Cell')
uo2_cell.setFill(self.materials['UO2'])
water_cell = openmoc.Cell(name='Water Cell')
water_cell.setFill(self.materials['Water'])
tube_cell = openmoc.Cell(name='Tube Cell')
tube_cell.setFill(self.materials['Guide Tube'])
# Create universes and fill with the associated cell
root_universe = openmoc.Universe(name='root universe')
root_universe.addCell(root_cell)
uo2 = openmoc.Universe(name='uo2 universe')
uo2.addCell(uo2_cell)
water = openmoc.Universe(name='water universe')
water.addCell(water_cell)
tube = openmoc.Universe(name='tube universe')
tube.addCell(tube_cell)
# Create the lattice and fill it with the appropriate universes
lattice = openmoc.Lattice(name='3x2 lattice')
lattice.setWidth(width_x=2.0, width_y=2.0)
lattice.setUniverses([[[uo2, tube, water], [water, uo2, tube]]])
root_cell.setFill(lattice)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(OblongLatticeGridInput, self).create_geometry()
def create_geometry(self):
"""Instantiate a 4x4 pin cell lattice Geometry."""
xmin = openmoc.XPlane(x=-2.0, name='xmin')
xmax = openmoc.XPlane(x=+2.0, name='xmax')
ymin = openmoc.YPlane(y=-2.0, name='ymin')
ymax = openmoc.YPlane(y=+2.0, name='ymax')
boundaries = [xmin, xmax, ymin, ymax]
if (self.dimensions == 3):
zmin = openmoc.ZPlane(z=-2.0, name='zmin')
zmax = openmoc.ZPlane(z=+2.0, name='zmax')
boundaries = [xmin, xmax, ymin, ymax, zmin, zmax]
for boundary in boundaries:
boundary.setBoundaryType(openmoc.REFLECTIVE)
if (self.dimensions == 3):
boundaries[-1].setBoundaryType(openmoc.VACUUM)
lat = self.create_lattice()
root_cell = openmoc.Cell(name='root cell')
root_cell.addSurface(halfspace=+1, surface=boundaries[0])
root_cell.addSurface(halfspace=-1, surface=boundaries[1])
root_cell.addSurface(halfspace=+1, surface=boundaries[2])
root_cell.addSurface(halfspace=-1, surface=boundaries[3])
if (self.dimensions == 3):
root_cell.addSurface(halfspace=+1, surface=boundaries[4])
root_cell.addSurface(halfspace=-1, surface=boundaries[5])
lattice_cell = openmoc.Cell(name='lattice cell')
assembly = openmoc.Universe(name='2x2 lattice')
root_universe = openmoc.Universe(name='root universe')
assembly.addCell(lattice_cell)
root_universe.addCell(root_cell)
lattice_cell.setFill(lat)
# 2x2 core
core = openmoc.Lattice(name='2x2 core')
core.setWidth(width_x=2.0, width_y=2.0)
core.setUniverses([[[assembly, assembly], [assembly, assembly]]])
root_cell.setFill(core)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(SimplerLatticeInput, self).create_geometry()
def create_geometry(self):
"""Instantiate an infinite medium lattice Geometry."""
length = 2.5
num_cells_x = 10
num_cells_y = 10
xmin = openmoc.XPlane(x=-length / 2., name='xmin')
xmax = openmoc.XPlane(x=+length / 2., name='xmax')
ymin = openmoc.YPlane(y=-length / 2., name='ymin')
ymax = openmoc.YPlane(y=+length / 2., name='ymax')
xmax.setBoundaryType(openmoc.REFLECTIVE)
xmin.setBoundaryType(openmoc.REFLECTIVE)
ymin.setBoundaryType(openmoc.REFLECTIVE)
ymax.setBoundaryType(openmoc.REFLECTIVE)
fill = openmoc.Cell(name='fill')
fill.setFill(self.materials['infinite medium'])
root_cell = openmoc.Cell(name='root cell')
root_cell.addSurface(halfspace=+1, surface=xmin)
root_cell.addSurface(halfspace=-1, surface=xmax)
root_cell.addSurface(halfspace=+1, surface=ymin)
root_cell.addSurface(halfspace=-1, surface=ymax)
fill_universe = openmoc.Universe(name='homogeneous fill cell')
fill_universe.addCell(fill)
root_universe = openmoc.Universe(name='root universe')
root_universe.addCell(root_cell)
lattice = openmoc.Lattice(name='MxN lattice')
lattice.setWidth(width_x=length / num_cells_x,
width_y=length / num_cells_y)
lattice.setUniverses([[[fill_universe] * num_cells_x] * num_cells_y])
root_cell.setFill(lattice)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(HomInfMedInput, self).create_geometry()
def get_openmoc_geometry(opencg_geometry):
if not isinstance(opencg_geometry, opencg.Geometry):
msg = 'Unable to get OpenMOC geometry from {0} which is ' \
'not an OpenCG Geometry object'.format(opencg_geometry)
raise ValueError(msg)
# Deep copy the goemetry since it may be modified to make all Surfaces
# compatible with OpenMOC's specifications
opencg_geometry.assignAutoIds()
opencg_geometry = copy.deepcopy(opencg_geometry)
# Update Cell bounding boxes in Geometry
opencg_geometry.updateBoundingBoxes()
# Clear dictionaries and auto-generated ID
OPENMOC_SURFACES.clear()
OPENCG_SURFACES.clear()
OPENMOC_CELLS.clear()
OPENCG_CELLS.clear()
OPENMOC_UNIVERSES.clear()
OPENCG_UNIVERSES.clear()
OPENMOC_LATTICES.clear()
OPENCG_LATTICES.clear()
# Make the entire geometry "compatible" before assigning auto IDs
universes = opencg_geometry.getAllUniverses()
for universe_id, universe in universes.items():
make_opencg_cells_compatible(universe)
opencg_geometry.assignAutoIds()
opencg_root_universe = opencg_geometry._root_universe
openmoc_root_universe = get_openmoc_universe(opencg_root_universe)
openmoc_geometry = openmoc.Geometry()
openmoc_geometry.setRootUniverse(openmoc_root_universe)
# FIXME
openmoc_geometry.thisown = 0
return openmoc_geometry
def _create_trackgenerator(self):
"""Dump and load the geometry then instantiate a TrackGenerator."""
# Geometry should be dumped before FSRs are initialized
# Dump the geometry
self.input_set.geometry.dumpToFile("geometry_file.geo")
# Get rid of the geometry
self.input_set.geometry = None
# Reload the geometry
self.input_set.geometry = openmoc.Geometry()
self.input_set.geometry.loadFromFile("geometry_file.geo")
# Instantiate a TrackGenerator
geometry = self.input_set.geometry
geometry.initializeFlatSourceRegions()
self.track_generator = \
openmoc.TrackGenerator(geometry, self.num_azim,
self.spacing)
def create_geometry(self):
"""Instantiate a 3x3 grid Geometry."""
# Create the planes that bound the cell and geometry
xplanes = [None] * 4
yplanes = [None] * 4
for i in range(4):
val = -3.0 + 6.0/3 * i
xplanes[i] = openmoc.XPlane(x=val, name='xplane' + str(i))
yplanes[i] = openmoc.YPlane(y=val, name='yplane' + str(i))
xplanes[0].setBoundaryType(openmoc.REFLECTIVE)
xplanes[-1].setBoundaryType(openmoc.REFLECTIVE)
yplanes[0].setBoundaryType(openmoc.REFLECTIVE)
yplanes[-1].setBoundaryType(openmoc.REFLECTIVE)
# Create the cells and set the central cell to UO2, the rest as water
cells = [[None]*3 for i in range(3)]
for i in range(3):
for j in range(3):
cells[i][j] = openmoc.Cell(name='Cell ' + str(3*i+j))
if i == 1 and j == 1:
cells[i][j].setFill(self.materials['UO2'])
else:
cells[i][j].setFill(self.materials['Water'])
cells[i][j].addSurface(halfspace=+1, surface=xplanes[i])
cells[i][j].addSurface(halfspace=-1, surface=xplanes[i+1])
cells[i][j].addSurface(halfspace=+1, surface=yplanes[j])
cells[i][j].addSurface(halfspace=-1, surface=yplanes[j+1])
# Add the cells to the universe
root_universe = openmoc.Universe(name='root universe')
for i in range(3):
for j in range(3):
root_universe.addCell(cells[i][j])
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(GridInput, self).create_geometry()
def _create_geometry(self):
"""Initialize CMFD and add it to the Geometry."""
self.input_set.geometry = openmoc.Geometry()
# load a geometry file with a non-uniform lattice
self.input_set.geometry.loadFromFile('non-uniform-lattice.geo')
# dump geometry file, to test compatibility with the load operation
self.input_set.geometry.dumpToFile('log/dump.geo')
# Initialize CMFD
cmfd = openmoc.Cmfd()
cmfd.setCMFDRelaxationFactor(0.7)
cmfd.setSORRelaxationFactor(1.0)
cmfd.setWidths([[0.05, 1.26, 1.26, 0.05], [0.05, 1.26, 1.26, 0.05],
[1., 1.5]])
cmfd.setGroupStructure([[1, 2, 3], [4, 5, 6, 7]])
cmfd.setCentroidUpdateOn(False)
# Add CMFD to the Geometry
self.input_set.geometry.setCmfd(cmfd)
lattice.setUniverses([[[pin1, pin2], [pin1, pin3]]])
lattice_cell.setFill(lattice)
# 2x2 core
core = openmoc.Lattice(name='2x2 core')
core.setWidth(width_x=2.0, width_y=2.0)
core.setUniverses([[[assembly, assembly], [assembly, assembly]]])
root_cell.setFill(core)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
geometry.setRootUniverse(root_universe)
###############################################################################
# Creating the TrackGenerator
###############################################################################
openmoc.log.py_printf('NORMAL', 'Initializing the track generator...')
track_generator = openmoc.TrackGenerator(geometry, opts.num_azim,
opts.track_spacing)
track_generator.setNumThreads(opts.num_omp_threads)
track_generator.generateTracks()
###############################################################################
# Running a Simulation
def create_geometry(self):
"""Instantiate a 4x4 non-uniform simple lattice Geometry."""
fuel_rings = 1
moderator_rings = 1
num_sectors = 8
openmoc.set_line_length(120)
r_fuel = 0.54
r_clad = 0.57
r_large = 0.60
pin_pitch = 1.26
gap_size = 0.05
surfaces = {}
surfaces['Pin Cell ZCylinder'] = openmoc.ZCylinder(
x=0, y=0, radius=r_fuel, name='Pin Cell ZCylinder')
surfaces['Clad Cell ZCylinder'] = openmoc.ZCylinder(
x=0, y=0, radius=r_clad, name='Clad Cell ZCylinder')
surfaces['large'] = openmoc.ZCylinder(x=0,
y=0,
radius=r_large,
name='large')
surfaces['z-inf'] = openmoc.ZPlane(z=-1.0E10)
surfaces['z+inf'] = openmoc.ZPlane(z=1.0E10)
cells = {}
cells['fuel'] = openmoc.Cell()
cells['clad'] = openmoc.Cell()
cells['mod'] = openmoc.Cell()
cells['uniform gap'] = openmoc.Cell()
cells['large_fuel'] = openmoc.Cell()
cells['large_mod'] = openmoc.Cell()
cells['fuel'].addSurface(halfspace=-1,
surface=surfaces['Pin Cell ZCylinder'])
cells['fuel'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['fuel'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['fuel'].setFill(self.materials['UO2'])
cells['fuel'].setNumSectors(num_sectors)
cells['fuel'].setNumRings(fuel_rings)
cells['clad'].addSurface(halfspace=+1,
surface=surfaces['Pin Cell ZCylinder'])
cells['clad'].addSurface(halfspace=-1,
surface=surfaces['Clad Cell ZCylinder'])
cells['clad'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['clad'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['clad'].setFill(self.materials['Clad'])
cells['clad'].setNumSectors(num_sectors)
cells['mod'].addSurface(halfspace=+1,
surface=surfaces['Clad Cell ZCylinder'])
cells['mod'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['mod'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['mod'].setFill(self.materials['Water'])
cells['mod'].setNumSectors(num_sectors)
cells['mod'].setNumRings(moderator_rings)
cells['uniform gap'].addSurface(halfspace=+1,
surface=surfaces['z-inf'])
cells['uniform gap'].addSurface(halfspace=-1,
surface=surfaces['z+inf'])
cells['uniform gap'].setFill(self.materials['Clad'])
cells['large_fuel'].addSurface(halfspace=-1, surface=surfaces['large'])
cells['large_fuel'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['large_fuel'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['large_fuel'].setFill(self.materials['UO2'])
cells['large_fuel'].setNumSectors(num_sectors)
cells['large_mod'].addSurface(halfspace=+1, surface=surfaces['large'])
cells['large_mod'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['large_mod'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['large_mod'].setFill(self.materials['Water'])
cells['large_mod'].setNumSectors(num_sectors)
universes = {}
universes['pin'] = openmoc.Universe()
universes['pin'].addCell(cells['fuel'])
universes['pin'].addCell(cells['clad'])
universes['pin'].addCell(cells['mod'])
universes['uniform gap'] = openmoc.Universe()
universes['uniform gap'].addCell(cells['uniform gap'])
universes['large_pin'] = openmoc.Universe()
universes['large_pin'].addCell(cells['large_fuel'])
universes['large_pin'].addCell(cells['large_mod'])
lower_left = [0., 0., 0.]
width = ([gap_size, pin_pitch, pin_pitch,
gap_size], [gap_size, pin_pitch, pin_pitch,
gap_size], [1.0, 1.5])
lattice = openmoc.Lattice(name='lattice with gap')
lattice.setWidths(width[0], width[1], width[2])
lattice.setOffset(lower_left[0] + sum(width[0]) / 2.,
lower_left[1] + sum(width[1]) / 2.,
lower_left[2] + sum(width[2]) / 2.)
f = universes['pin']
g = universes['uniform gap']
l = universes['large_pin']
lattice.setUniverses([[[g, g, g, g], [g, f, f, g], [g, f, f, g],
[g, g, g, g]],
[[g, g, g, g], [g, f, f, g], [g, f, f, g],
[g, g, g, g]]])
surfaces['Global x-'] = openmoc.XPlane(x=lower_left[0])
surfaces['Global x+'] = openmoc.XPlane(x=lower_left[0] + sum(width[0]))
surfaces['Global y-'] = openmoc.YPlane(y=lower_left[1])
surfaces['Global y+'] = openmoc.YPlane(y=lower_left[1] + sum(width[1]))
surfaces['Global z-'] = openmoc.ZPlane(z=lower_left[2])
surfaces['Global z+'] = openmoc.ZPlane(z=lower_left[2] + sum(width[2]))
surfaces['Global x-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global x+'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global y-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global y+'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global z-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global z+'].setBoundaryType(openmoc.REFLECTIVE)
root_cell = openmoc.Cell()
root_cell.setFill(lattice)
root_cell.addSurface(halfspace=+1, surface=surfaces['Global x-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global x+'])
root_cell.addSurface(halfspace=+1, surface=surfaces['Global y-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global y+'])
root_cell.addSurface(halfspace=+1, surface=surfaces['Global z-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global z+'])
root_universe = openmoc.Universe()
root_universe.addCell(root_cell)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(NonUniformLatticeInput, self).create_geometry()
def get_openmoc_geometry(opencg_geometry):
"""Return an OpenMOC geometry corresponding to an OpenCG geometry.
Parameters
----------
opencg_geometry : opencg.Geometry
OpenCG geometry
Returns
-------
openmoc_geometry : openmoc.Geometry
Equivalent OpenMOC geometry
"""
cv.check_type('opencg_geometry', opencg_geometry, opencg.Geometry)
# Deep copy the goemetry since it may be modified to make all Surfaces
# compatible with OpenMOC's specifications
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 IDs
OPENMOC_MATERIALS.clear()
OPENCG_MATERIALS.clear()
OPENMOC_SURFACES.clear()
OPENCG_SURFACES.clear()
OPENMOC_CELLS.clear()
OPENCG_CELLS.clear()
OPENMOC_UNIVERSES.clear()
OPENCG_UNIVERSES.clear()
OPENMOC_LATTICES.clear()
OPENCG_LATTICES.clear()
# Make the entire geometry "compatible" before assigning auto IDs
universes = opencg_geometry.get_all_universes()
for universe_id, universe in universes.items():
make_opencg_cells_compatible(universe)
opencg_geometry.assign_auto_ids()
opencg_root_universe = opencg_geometry.root_universe
openmoc_root_universe = get_openmoc_universe(opencg_root_universe)
openmoc_geometry = openmoc.Geometry()
openmoc_geometry.setRootUniverse(openmoc_root_universe)
# Update OpenMOC's auto-generated object IDs (e.g., Surface, Material)
# with the maximum of those created from the OpenCG objects
all_materials = openmoc_geometry.getAllMaterials()
all_surfaces = openmoc_geometry.getAllSurfaces()
all_cells = openmoc_geometry.getAllCells()
all_universes = openmoc_geometry.getAllUniverses()
max_material_id = max(all_materials.keys())
max_surface_id = max(all_surfaces.keys())
max_cell_id = max(all_cells.keys())
max_universe_id = max(all_universes.keys())
openmoc.maximize_material_id(max_material_id + 1)
openmoc.maximize_surface_id(max_surface_id + 1)
openmoc.maximize_cell_id(max_cell_id + 1)
openmoc.maximize_universe_id(max_universe_id + 1)
return openmoc_geometry
def create_geometry(self):
"""Instantiate 4x4 non-uniform and axially extended lattice problem."""
fuel_rings = 1
moderator_rings = 1
num_sectors = 8
openmoc.set_line_length(120)
r_fuel = 0.54
r_clad = 0.57
r_large = 0.60
pin_pitch = 1.26
gap_size = 0.05
surfaces = {}
surfaces['Pin Cell ZCylinder'] = openmoc.ZCylinder(
x=0, y=0, radius=r_fuel, name='Pin Cell ZCylinder')
surfaces['Clad Cell ZCylinder'] = openmoc.ZCylinder(
x=0, y=0, radius=r_clad, name='Clad Cell ZCylinder')
surfaces['large'] = openmoc.ZCylinder(x=0,
y=0,
radius=r_large,
name='large')
surfaces['z-inf'] = openmoc.ZPlane(z=-1.0E10)
surfaces['z+inf'] = openmoc.ZPlane(z=1.0E10)
cells = {}
cells['fuel'] = openmoc.Cell()
cells['clad'] = openmoc.Cell()
cells['mod'] = openmoc.Cell()
cells['uniform gap'] = openmoc.Cell()
cells['large_fuel'] = openmoc.Cell()
cells['large_mod'] = openmoc.Cell()
cells['fuel'].addSurface(halfspace=-1,
surface=surfaces['Pin Cell ZCylinder'])
cells['fuel'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['fuel'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['fuel'].setFill(self.materials['UO2'])
cells['fuel'].setNumSectors(num_sectors)
cells['fuel'].setNumRings(fuel_rings)
cells['clad'].addSurface(halfspace=+1,
surface=surfaces['Pin Cell ZCylinder'])
cells['clad'].addSurface(halfspace=-1,
surface=surfaces['Clad Cell ZCylinder'])
cells['clad'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['clad'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['clad'].setFill(self.materials['Clad'])
cells['clad'].setNumSectors(num_sectors)
cells['mod'].addSurface(halfspace=+1,
surface=surfaces['Clad Cell ZCylinder'])
cells['mod'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['mod'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['mod'].setFill(self.materials['Water'])
cells['mod'].setNumSectors(num_sectors)
cells['mod'].setNumRings(moderator_rings)
cells['uniform gap'].addSurface(halfspace=+1,
surface=surfaces['z-inf'])
cells['uniform gap'].addSurface(halfspace=-1,
surface=surfaces['z+inf'])
cells['uniform gap'].setFill(self.materials['Clad'])
cells['large_fuel'].addSurface(halfspace=-1, surface=surfaces['large'])
cells['large_fuel'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['large_fuel'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['large_fuel'].setFill(self.materials['UO2'])
cells['large_fuel'].setNumSectors(num_sectors)
cells['large_mod'].addSurface(halfspace=+1, surface=surfaces['large'])
cells['large_mod'].addSurface(halfspace=+1, surface=surfaces['z-inf'])
cells['large_mod'].addSurface(halfspace=-1, surface=surfaces['z+inf'])
cells['large_mod'].setFill(self.materials['Water'])
cells['large_mod'].setNumSectors(num_sectors)
universes = {}
universes['pin'] = openmoc.Universe()
universes['pin'].addCell(cells['fuel'])
universes['pin'].addCell(cells['clad'])
universes['pin'].addCell(cells['mod'])
universes['uniform gap'] = openmoc.Universe()
universes['uniform gap'].addCell(cells['uniform gap'])
universes['large_pin'] = openmoc.Universe()
universes['large_pin'].addCell(cells['large_fuel'])
universes['large_pin'].addCell(cells['large_mod'])
lower_left = [0., 0., 0.]
# set the XYZ widths of non-uniform lattice
width = ([gap_size, pin_pitch, pin_pitch,
gap_size], [gap_size, pin_pitch, pin_pitch,
gap_size], [1.0] * 20)
lattice = openmoc.Lattice(name='lattice with gap')
lattice.setWidths(width[0], width[1], width[2])
lattice.setOffset(lower_left[0] + sum(width[0]) / 2.,
lower_left[1] + sum(width[1]) / 2.,
lower_left[2] + sum(width[2]) / 2.)
f = universes['pin']
g = universes['uniform gap']
l = universes['large_pin']
a = numpy.array([[g, g, g, g], [g, f, f, g], [g, f, f, g],
[g, g, g, g]])
fill_universes = numpy.tile(a, (20, 1, 1))
# make the geometry axially heterogeneous
fill_universes[2][1][1] = g
fill_universes = fill_universes.tolist()
lattice.setUniverses(fill_universes)
surfaces['Global x-'] = openmoc.XPlane(x=lower_left[0])
surfaces['Global x+'] = openmoc.XPlane(x=lower_left[0] + sum(width[0]))
surfaces['Global y-'] = openmoc.YPlane(y=lower_left[1])
surfaces['Global y+'] = openmoc.YPlane(y=lower_left[1] + sum(width[1]))
surfaces['Global z-'] = openmoc.ZPlane(z=lower_left[2])
surfaces['Global z+'] = openmoc.ZPlane(z=lower_left[2] + sum(width[2]))
surfaces['Global x-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global x+'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global y-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global y+'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global z-'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Global z+'].setBoundaryType(openmoc.REFLECTIVE)
root_cell = openmoc.Cell()
root_cell.setFill(lattice)
root_cell.addSurface(halfspace=+1, surface=surfaces['Global x-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global x+'])
root_cell.addSurface(halfspace=+1, surface=surfaces['Global y-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global y+'])
root_cell.addSurface(halfspace=+1, surface=surfaces['Global z-'])
root_cell.addSurface(halfspace=-1, surface=surfaces['Global z+'])
root_universe = openmoc.Universe()
root_universe.addCell(root_cell)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(AxialExtendedInput, self).create_geometry()
def _create_geometry(self):
"""Inspired from SimpleLattice"""
self.materials = \
openmoc.materialize.load_from_hdf5(filename='c5g7-mgxs.h5',
directory='../../sample-input/')
xmin = openmoc.XPlane(x=-2.0, name='xmin')
xmax = openmoc.XPlane(x=+2.0, name='xmax')
ymin = openmoc.YPlane(y=-2.0, name='ymin')
ymax = openmoc.YPlane(y=+2.0, name='ymax')
boundaries = [xmin, xmax, ymin, ymax]
if (self.dimensions == 3):
zmin = openmoc.ZPlane(z=-5.0, name='zmin')
zmax = openmoc.ZPlane(z=+5.0, name='zmax')
boundaries = [xmin, xmax, ymin, ymax, zmin, zmax]
large_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.4, name='large pin')
medium_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.3, name='medium pin')
small_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.2, name='small pin')
xplane = openmoc.XPlane(x=0, name='mid-cell')
yplane = openmoc.YPlane(y=0, name='mid-cell')
for boundary in boundaries: boundary.setBoundaryType(openmoc.REFLECTIVE)
if (self.dimensions == 3):
boundaries[-1].setBoundaryType(openmoc.VACUUM)
large_fuel = openmoc.Cell(name='large pin fuel')
large_fuel.setNumRings(3)
large_fuel.setNumSectors(8)
large_fuel.setFill(self.materials['UO2'])
large_fuel.addSurface(halfspace=-1, surface=large_zcylinder)
large_moderator = openmoc.Cell(name='large pin moderator')
large_moderator.setNumSectors(8)
large_moderator.setFill(self.materials['Water'])
large_moderator.addSurface(halfspace=+1, surface=large_zcylinder)
medium_fuel = openmoc.Cell(name='medium pin fuel')
medium_fuel.setNumRings(3)
medium_fuel.setNumSectors(8)
medium_fuel.setFill(self.materials['UO2'])
medium_fuel.addSurface(halfspace=-1, surface=medium_zcylinder)
medium_moderator = openmoc.Cell(name='medium pin moderator')
medium_moderator.setNumSectors(8)
medium_moderator.setFill(self.materials['Water'])
medium_moderator.addSurface(halfspace=+1, surface=medium_zcylinder)
small_fuel = openmoc.Cell(name='small pin fuel')
small_fuel.setNumRings(3) # test may fail if fsrs are initialized
small_fuel.setNumSectors(8)
small_fuel.setFill(self.materials['UO2'])
small_fuel.addSurface(halfspace=-1, surface=small_zcylinder)
small_clad_q1 = openmoc.Cell(name='small pin cladding quarter')
small_clad_q1.setFill(self.materials['Clad'])
small_clad_q1.addSurface(halfspace=+1, surface=small_zcylinder)
small_clad_q1.addSurface(halfspace=-1, surface=medium_zcylinder)
small_clad_q1.addSurface(halfspace=+1, surface=xplane)
small_clad_q1.addSurface(halfspace=-1, surface=yplane)
small_moderator = openmoc.Cell(name='small pin moderator')
small_moderator.setNumSectors(8)
small_moderator.setFill(self.materials['Water'])
small_moderator.addSurface(halfspace=+1, surface=medium_zcylinder)
lattice_cell = openmoc.Cell(name='lattice cell')
root_cell = openmoc.Cell(name='root cell')
root_cell.addSurface(halfspace=+1, surface=boundaries[0])
root_cell.addSurface(halfspace=-1, surface=boundaries[1])
root_cell.addSurface(halfspace=+1, surface=boundaries[2])
root_cell.addSurface(halfspace=-1, surface=boundaries[3])
if (self.dimensions == 3):
root_cell.addSurface(halfspace=+1, surface=boundaries[4])
root_cell.addSurface(halfspace=-1, surface=boundaries[5])
pin1 = openmoc.Universe(name='large pin cell')
pin2 = openmoc.Universe(name='medium pin cell')
pin3 = openmoc.Universe(name='small pin cell')
assembly = openmoc.Universe(name='2x2 lattice')
root_universe = openmoc.Universe(name='root universe')
pin1.addCell(large_fuel)
pin1.addCell(large_moderator)
pin2.addCell(medium_fuel)
pin2.addCell(medium_moderator)
pin3.addCell(small_fuel)
pin3.addCell(small_clad_q1)
pin3.addCell(small_moderator)
assembly.addCell(lattice_cell)
root_universe.addCell(root_cell)
# 2x2 assembly
lattice = openmoc.Lattice(name='2x2 lattice')
lattice.setWidth(width_x=1.0, width_y=1.0)
lattice.setUniverses([[[pin1, pin2], [pin1, pin3]]])
lattice_cell.setFill(lattice)
# Rotate a lattice to test rotation of a fill cell
assembly_c = openmoc.Cell(name='rotated cell containing a lattice')
assembly_c.setFill(assembly)
assembly_c.setRotation((0,0,90), 'degrees')
assembly_r = openmoc.Universe(name='rotated lattice')
assembly_r.addCell(assembly_c)
# Translate a lattice to test translation of a fill cell
assembly_c = openmoc.Cell(name='rotated cell containing a lattice')
assembly_c.setFill(assembly)
assembly_c.setTranslation((0.05,0,0))
assembly_t = openmoc.Universe(name='translated lattice')
assembly_t.addCell(assembly_c)
# Rotate a lattice to test rotation of a fill cell
assembly_c = openmoc.Cell(name='translated cell containing a lattice')
assembly_c.setFill(assembly)
assembly_c.setRotation((0,0,-90), 'degrees')
assembly_c.setTranslation((-0.05,0,0))
assembly_rt = openmoc.Universe(name='translate and rotated lattice')
assembly_rt.addCell(assembly_c)
# 2x2 core
core = openmoc.Lattice(name='2x2 core')
core.setWidth(width_x=2.0, width_y=2.0)
core.setUniverses([[[assembly, assembly_rt], [assembly_t, assembly_r]]])
root_cell.setFill(core)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
def _run_openmoc(self):
"""Instantiate a complex region Geometry."""
root_universe = openmoc.Universe(name='root universe')
root_cell = openmoc.Cell(name='root cell')
root_universe.addCell(root_cell)
u1 = openmoc.Universe(name='universe 1')
u2 = openmoc.Universe(name='universe 2 in c2')
root_cell.setFill(u1)
# Z-bounds at root level
p1 = openmoc.ZPlane(z=-2.0, name='zmin')
p1.setBoundaryType(openmoc.REFLECTIVE)
p2 = openmoc.ZPlane(z=+2.0, name='zmax')
p2.setBoundaryType(openmoc.INTERFACE)
root_cell.addSurface(halfspace=+1, surface=p1)
root_cell.addSurface(halfspace=-1, surface=p2)
# Cells in the root cell
c1 = openmoc.Cell(name='intersection cell')
c2 = openmoc.Cell(name='union cell')
c2a = openmoc.Cell(name='union cell 2')
c3 = openmoc.Cell(name='unbound cell')
u1.addCell(c1)
u1.addCell(c2)
u1.addCell(c3)
# Setting the parent cell helps to find boundaries (in Z here)
c3.setParent(root_cell)
# Cell c2a in c2, to further test arborescence
c2.setFill(u2)
u2.addCell(c2a)
c2.setParent(root_cell)
c2a.setParent(c2) # to test transitivity
# Bounds for cell 1 : intersection region cell
p11 = openmoc.XPlane(x=-2.0, name='xmin')
p11.setBoundaryType(openmoc.REFLECTIVE)
p12 = openmoc.YPlane(y=-2.0, name='ymin')
p12.setBoundaryType(openmoc.VACUUM)
p13 = openmoc.ZCylinder(x=0, y=0, radius=2.5, name='cylinder')
p13.setBoundaryType(openmoc.INTERFACE)
# addSurface assumes an intersection, which is what we want here
c1.addSurface(halfspace=+1, surface=p11)
c1.addSurface(halfspace=+1, surface=p12)
c1.addSurface(halfspace=-1, surface=p13)
# Bounds for cell 2 : union region cell
p22 = openmoc.ZCylinder(x=4, y=4, radius=2.5, name='cylinder')
p22.setBoundaryType(openmoc.INTERFACE)
p23 = openmoc.ZCylinder(x=-2, y=-8, radius=3, name='cylinder')
p23.setBoundaryType(openmoc.VACUUM)
# To have a union, we need to use addLogicalNode and addSurfaceInRegion
c2.addLogicalNode(1)
c2.addSurfaceInRegion(halfspace=-1, surface=p22)
c2.addSurfaceInRegion(halfspace=-1, surface=p23)
# Plane limits area even more
c2a.addLogicalNode(1)
c2a.addSurfaceInRegion(halfspace=+1, surface=p11)
# Add a material to a cell to know the number of groups
c1.setFill(self.materials['UO2'])
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
# Dump geometry
self.geometry.dumpToFile("geometry_file.geo")
# Get rid of the geometry
self.geometry = None
# Reload the geometry
self.geometry = openmoc.Geometry()
self.geometry.loadFromFile("geometry_file.geo")
# Dump geometry again
self.geometry.dumpToFile("geometry_file_second.geo")
def create_geometry(self):
"""Instantiate a 17x17 pin cell lattice Geometry."""
# Create ZCylinder for the fuel and moderator
fuel_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.54)
# Create planes to bound the entire geometry
xmin = openmoc.XPlane(x=-10.71, name='xmin')
xmax = openmoc.XPlane(x=+10.71, name='xmax')
ymin = openmoc.YPlane(y=-10.71, name='ymin')
ymax = openmoc.YPlane(y=+10.71, name='xmax')
xmin.setBoundaryType(openmoc.REFLECTIVE)
xmax.setBoundaryType(openmoc.REFLECTIVE)
ymin.setBoundaryType(openmoc.REFLECTIVE)
ymax.setBoundaryType(openmoc.REFLECTIVE)
# 4.3% MOX pin cell
mox43_cell = openmoc.Cell()
mox43_cell.setFill(self.materials['MOX-4.3%'])
mox43_cell.setNumRings(3)
mox43_cell.setNumSectors(8)
mox43_cell.addSurface(-1, fuel_radius)
mox43 = openmoc.Universe(name='MOX-4.3%')
mox43.addCell(mox43_cell)
# 7% MOX pin cell
mox7_cell = openmoc.Cell()
mox7_cell.setFill(self.materials['MOX-7%'])
mox7_cell.setNumRings(3)
mox7_cell.setNumSectors(8)
mox7_cell.addSurface(-1, fuel_radius)
mox7 = openmoc.Universe(name='MOX-7%')
mox7.addCell(mox7_cell)
# 8.7% MOX pin cell
mox87_cell = openmoc.Cell()
mox87_cell.setFill(self.materials['MOX-8.7%'])
mox87_cell.setNumRings(3)
mox87_cell.setNumSectors(8)
mox87_cell.addSurface(-1, fuel_radius)
mox87 = openmoc.Universe(name='MOX-8.7%')
mox87.addCell(mox87_cell)
# Fission chamber pin cell
fission_chamber_cell = openmoc.Cell()
fission_chamber_cell.setFill(self.materials['Fission Chamber'])
fission_chamber_cell.setNumRings(3)
fission_chamber_cell.setNumSectors(8)
fission_chamber_cell.addSurface(-1, fuel_radius)
fission_chamber = openmoc.Universe(name='Fission Chamber')
fission_chamber.addCell(fission_chamber_cell)
# Guide tube pin cell
guide_tube_cell = openmoc.Cell()
guide_tube_cell.setFill(self.materials['Guide Tube'])
guide_tube_cell.setNumRings(3)
guide_tube_cell.setNumSectors(8)
guide_tube_cell.addSurface(-1, fuel_radius)
guide_tube = openmoc.Universe(name='Guide Tube')
guide_tube.addCell(guide_tube_cell)
# Moderator cell
moderator = openmoc.Cell()
moderator.setFill(self.materials['Water'])
moderator.addSurface(+1, fuel_radius)
moderator.setNumRings(3)
moderator.setNumSectors(8)
# Add moderator to each pin cell
pins = [mox43, mox7, mox87, fission_chamber, guide_tube]
for pin in pins:
pin.addCell(moderator)
# CellFills for the assembly
assembly1_cell = openmoc.Cell(name='Assembly 1')
assembly1 = openmoc.Universe(name='Assembly 1')
assembly1.addCell(assembly1_cell)
# A mixed enrichment PWR MOX fuel assembly
assembly = openmoc.Lattice(name='MOX Assembly')
assembly.setWidth(width_x=1.26, width_y=1.26)
# Create a template to map to pin cell types
template = [[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 1],
[1, 2, 2, 2, 2, 4, 2, 2, 4, 2, 2, 4, 2, 2, 2, 2, 1],
[1, 2, 2, 4, 2, 3, 3, 3, 3, 3, 3, 3, 2, 4, 2, 2, 1],
[1, 2, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 2, 1],
[1, 2, 4, 3, 3, 4, 3, 3, 4, 3, 3, 4, 3, 3, 4, 2, 1],
[1, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 1],
[1, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 1],
[1, 2, 4, 3, 3, 4, 3, 3, 5, 3, 3, 4, 3, 3, 4, 2, 1],
[1, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 1],
[1, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 1],
[1, 2, 4, 3, 3, 4, 3, 3, 4, 3, 3, 4, 3, 3, 4, 2, 1],
[1, 2, 2, 2, 3, 3, 3, 3, 3, 3, 3, 3, 3, 2, 2, 2, 1],
[1, 2, 2, 4, 2, 3, 3, 3, 3, 3, 3, 3, 2, 4, 2, 2, 1],
[1, 2, 2, 2, 2, 4, 2, 2, 4, 2, 2, 4, 2, 2, 2, 2, 1],
[1, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 2, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1]]
universes = {1 : mox43, 2 : mox7, 3 : mox87,
4 : guide_tube, 5 : fission_chamber}
for i in range(17):
for j in range(17):
template[i][j] = universes[template[i][j]]
assembly.setUniverses([template])
# Root Cell/Universe
root_cell = openmoc.Cell(name='Full Geometry')
root_cell.setFill(assembly)
root_cell.addSurface(+1, xmin)
root_cell.addSurface(-1, xmax)
root_cell.addSurface(+1, ymin)
root_cell.addSurface(-1, ymax)
root_universe = openmoc.Universe(name='Root Universe')
root_universe.addCell(root_cell)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(PwrAssemblyInput, self).create_geometry()
def create_geometry(self):
"""Instantiate a 4x4 pin cell lattice Geometry."""
xmin = openmoc.XPlane(x=-2.0, name='xmin')
xmax = openmoc.XPlane(x=+2.0, name='xmax')
ymax = openmoc.YPlane(y=+2.0, name='ymin')
ymin = openmoc.YPlane(y=-2.0, name='ymax')
boundaries = [xmin, xmax, ymin, ymax]
large_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.4, name='large pin')
medium_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.3, name='medium pin')
small_zcylinder = openmoc.ZCylinder(x=0.0, y=0.0,
radius=0.2, name='small pin')
for boundary in boundaries: boundary.setBoundaryType(openmoc.REFLECTIVE)
large_fuel = openmoc.Cell(name='large pin fuel')
large_fuel.setNumRings(3)
large_fuel.setNumSectors(8)
large_fuel.setFill(self.materials['UO2'])
large_fuel.addSurface(halfspace=-1, surface=large_zcylinder)
large_moderator = openmoc.Cell(name='large pin moderator')
large_moderator.setNumSectors(8)
large_moderator.setFill(self.materials['Water'])
large_moderator.addSurface(halfspace=+1, surface=large_zcylinder)
medium_fuel = openmoc.Cell(name='medium pin fuel')
medium_fuel.setNumRings(3)
medium_fuel.setNumSectors(8)
medium_fuel.setFill(self.materials['UO2'])
medium_fuel.addSurface(halfspace=-1, surface=medium_zcylinder)
medium_moderator = openmoc.Cell(name='medium pin moderator')
medium_moderator.setNumSectors(8)
medium_moderator.setFill(self.materials['Water'])
medium_moderator.addSurface(halfspace=+1, surface=medium_zcylinder)
small_fuel = openmoc.Cell(name='small pin fuel')
small_fuel.setNumRings(3)
small_fuel.setNumSectors(8)
small_fuel.setFill(self.materials['UO2'])
small_fuel.addSurface(halfspace=-1, surface=small_zcylinder)
small_moderator = openmoc.Cell(name='small pin moderator')
small_moderator.setNumSectors(8)
small_moderator.setFill(self.materials['Water'])
small_moderator.addSurface(halfspace=+1, surface=small_zcylinder)
lattice_cell = openmoc.Cell(name='lattice cell')
root_cell = openmoc.Cell(name='root cell')
root_cell.addSurface(halfspace=+1, surface=boundaries[0])
root_cell.addSurface(halfspace=-1, surface=boundaries[1])
root_cell.addSurface(halfspace=+1, surface=boundaries[2])
root_cell.addSurface(halfspace=-1, surface=boundaries[3])
pin1 = openmoc.Universe(name='large pin cell')
pin2 = openmoc.Universe(name='medium pin cell')
pin3 = openmoc.Universe(name='small pin cell')
assembly = openmoc.Universe(name='2x2 lattice')
root_universe = openmoc.Universe(name='root universe')
pin1.addCell(large_fuel)
pin1.addCell(large_moderator)
pin2.addCell(medium_fuel)
pin2.addCell(medium_moderator)
pin3.addCell(small_fuel)
pin3.addCell(small_moderator)
assembly.addCell(lattice_cell)
root_universe.addCell(root_cell)
# 2x2 assembly
lattice = openmoc.Lattice(name='2x2 lattice')
lattice.setWidth(width_x=1.0, width_y=1.0)
lattice.setUniverses([[[pin1, pin2], [pin1, pin3]]])
lattice_cell.setFill(lattice)
# 2x2 core
core = openmoc.Lattice(name='2x2 core')
core.setWidth(width_x=2.0, width_y=2.0)
core.setUniverses([[[assembly, assembly], [assembly, assembly]]])
root_cell.setFill(core)
self.geometry = openmoc.Geometry()
self.geometry.setRootUniverse(root_universe)
super(SimpleLatticeInput, self).create_geometry()
def _run_openmoc(self):
runtime = openmoc.RuntimeParameters()
string_input = [
'-debug', '1', '-log_level', 'NORMAL', '-domain_decompose',
'2,2,2', '-num_domain_modules', '1,1,1', '-num_threads', '1',
'-log_filename', 'test_problem.log', '-geo_filename',
'geometry_file.geo', '-azim_spacing', '0.22 ', '-num_azim', '4',
'-polar_spacing', '0.8', '-num_polar', '6', '-seg_zones',
'-5.0,5.0', '-segmentation_type', '3', '-quadraturetype', '2',
'-CMFD_group_structure', '1/2,3,4/5,6,7', '-CMFD_lattice', '2,3,3',
'-widths_x', '1,2*1,1', '-widths_y', '1,2*1,1', '-widths_z',
'3.5,2.5*2,1.5', '-CMFD_flux_update_on', '1', '-knearest', '2',
'-CMFD_centroid_update_on', '1', '-use_axial_interpolation', '2',
'-SOR_factor', '1.5', '-CMFD_relaxation_factor', '0.7',
'-ls_solver', '1', '-max_iters', '15', '-MOC_src_residual_type',
'1', '-MOC_src_tolerance', '1.0E-2', '-output_mesh_lattice',
'-output_mesh_lattice', ' 5,5,9', ' -output_type', ' 0',
'-output_mesh_lattice', '-output_mesh_lattice', ' 5,5,9',
' -output_type', ' 1', '-non_uniform_output',
'1.26*3/1*3/4.*3/-1.,1.,-1.', ' -output_type 1 ',
'-verbose_report', '1', '-time_report', '1'
]
string_input = [s.encode('utf8') for s in string_input]
runtime.setRuntimeParameters(string_input)
print(string_input)
# Define simulation parameters
num_threads = runtime._num_threads
# Set logging information
if (runtime._log_filename):
openmoc.set_log_filename(runtime._log_filename)
openmoc.set_log_level(runtime._log_level)
openmoc.set_line_length(120)
py_printf('NORMAL', 'Geometry file = %s', runtime._geo_filename)
py_printf('NORMAL', 'Azimuthal spacing = %f', runtime._azim_spacing)
py_printf('NORMAL', 'Azimuthal angles = %d', runtime._num_azim)
py_printf('NORMAL', 'Polar spacing = %f', runtime._polar_spacing)
py_printf('NORMAL', 'Polar angles = %d', runtime._num_polar)
# Create the geometry
py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
self.input_set.geometry = geometry
if (not runtime._geo_filename):
py_printf('ERROR', 'No geometry file is provided')
geometry.loadFromFile(runtime._geo_filename)
if False: #FIXME
geometry.setDomainDecomposition(runtime._NDx, runtime._NDy,
runtime._NDz, MPI_COMM_WORLD)
geometry.setNumDomainModules(runtime._NMx, runtime._NMy, runtime._NMz)
if ((runtime._NCx > 0 and runtime._NCy > 0 and runtime._NCz > 0)
or (not runtime._cell_widths_x.empty()
and not runtime._cell_widths_y.empty()
and not runtime._cell_widths_z.empty())):
# Create CMFD mesh
py_printf('NORMAL', 'Creating CMFD mesh...')
cmfd = openmoc.Cmfd()
cmfd.setSORRelaxationFactor(runtime._SOR_factor)
cmfd.setCMFDRelaxationFactor(runtime._CMFD_relaxation_factor)
if (runtime._cell_widths_x.empty()
or runtime._cell_widths_y.empty()
or runtime._cell_widths_z.empty()):
cmfd.setLatticeStructure(runtime._NCx, runtime._NCy,
runtime._NCz)
else:
cmfd_widths = [
runtime._cell_widths_x, runtime._cell_widths_y,
runtime._cell_widths_z
]
cmfd.setWidths(cmfd_widths)
if (not runtime._CMFD_group_structure.empty()):
cmfd.setGroupStructure(runtime._CMFD_group_structure)
cmfd.setKNearest(runtime._knearest)
cmfd.setCentroidUpdateOn(runtime._CMFD_centroid_update_on)
cmfd.useAxialInterpolation(runtime._use_axial_interpolation)
geometry.setCmfd(cmfd)
geometry.initializeFlatSourceRegions()
# Initialize track generator and generate tracks
py_printf('NORMAL', 'Initializing the track generator...')
if runtime._quadraturetype == 0:
quad = openmoc.TYPolarQuad()
if runtime._quadraturetype == 1:
quad = openmoc.LeonardPolarQuad()
if runtime._quadraturetype == 2:
quad = openmoc.GLPolarQuad()
if runtime._quadraturetype == 3:
quad = openmoc.EqualWeightPolarQuad()
if runtime._quadraturetype == 4:
quad = openmoc.EqualAnglePolarQuad()
quad.setNumAzimAngles(runtime._num_azim)
quad.setNumPolarAngles(runtime._num_polar)
track_generator = openmoc.TrackGenerator3D(geometry, runtime._num_azim,
runtime._num_polar,
runtime._azim_spacing,
runtime._polar_spacing)
track_generator.setNumThreads(num_threads)
track_generator.setQuadrature(quad)
track_generator.setSegmentFormation(runtime._segmentation_type)
if (len(runtime._seg_zones) > 0):
track_generator.setSegmentationZones(runtime._seg_zones)
track_generator.generateTracks()
self.track_generator = track_generator
# Initialize solver and run simulation
if (runtime._linear_solver):
self.solver = openmoc.CPULSSolver(track_generator)
else:
self.solver = openmoc.CPUSolver(track_generator)
if (runtime._verbose_report):
self.solver.setVerboseIterationReport()
self.solver.setNumThreads(num_threads)
self.solver.setConvergenceThreshold(runtime._tolerance)
self.solver.computeEigenvalue(runtime._max_iters,
runtime._MOC_src_residual_type)
if (runtime._time_report):
self.solver.printTimerReport()
# Extract reaction rates
my_rank = 0
#if False: #FIXME
#MPI_Comm_rank(MPI_COMM_WORLD, &my_rank);
rxtype = {'FISSION_RX', 'TOTAL_RX', 'ABSORPTION_RX', 'FLUX_RX'}