def test_ids(self):
openmoc.reset_universe_id()
lattice_2 = openmoc.Lattice()
self.assertEqual(lattice_2.getId(), 1000016)
openmoc.maximize_universe_id(10000000)
lattice_3 = openmoc.Lattice()
self.assertEqual(lattice_3.getId(), 10000000)
def __init__(self):
# define fuel assembly basic parameters
# CellFills for the assembly
self.assembly1_cell = openmoc.Cell(name='Fuel Assembly')
self.assembly1 = openmoc.Universe(name='Fuel Assembly')
self.assembly1.addCell(self.assembly1_cell)
# A mixed enrichment PWR MOX fuel assembly
self.assembly = openmoc.Lattice(name='UOX Assembly')
self.assembly.setWidth(width_x=1.26, width_y=1.26)
# Create a template to map to pin cell types
self.template = [[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 1, 1, 1],
[1, 1, 1, 4, 1, 1, 1, 1, 1, 1, 1, 1, 1, 4, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 4, 1, 1, 4, 1, 1, 1, 1, 1, 4, 1, 1, 4, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 4, 1, 1, 1, 1, 1, 1, 1, 1, 1, 4, 1, 1, 1],
[1, 1, 1, 1, 1, 4, 1, 1, 4, 1, 1, 4, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1]]
self.root_cell = []
self.root_universe = []
def get_openmoc_lattice(opencg_lattice):
"""Return an OpenMOC lattice corresponding to an OpenCG lattice.
Parameters
----------
opencg_lattice : opencg.Lattice
OpenCG lattice
Returns
-------
openmoc_lattice : openmoc.Lattice
Equivalent OpenMOC lattice
"""
cv.check_type('opencg_lattice', opencg_lattice, opencg.Lattice)
global OPENMOC_LATTICES
lattice_id = opencg_lattice.id
# If this Lattice was already created, use it
if lattice_id in OPENMOC_LATTICES:
return OPENMOC_LATTICES[lattice_id]
name = str(opencg_lattice.name)
dimension = opencg_lattice.dimension
width = opencg_lattice.width
offset = opencg_lattice.offset
universes = opencg_lattice.universes
# Initialize an empty array for the OpenMOC nested Universes in this Lattice
universe_array = np.ndarray(tuple(dimension[::-1]), dtype=openmoc.Universe)
# Create OpenMOC Universes for each unique nested Universe in this Lattice
unique_universes = opencg_lattice.get_unique_universes()
for universe_id, universe in unique_universes.items():
unique_universes[universe_id] = get_openmoc_universe(universe)
# Build the nested Universe array
for z in range(dimension[2]):
for y in range(dimension[1]):
for x in range(dimension[0]):
universe_id = universes[z][y][x].id
universe_array[z][dimension[1] - y -
1][x] = unique_universes[universe_id]
openmoc_lattice = openmoc.Lattice(lattice_id, name)
openmoc_lattice.setWidth(width[0], width[1], width[2])
openmoc_lattice.setUniverses(universe_array.tolist())
openmoc_lattice.setOffset(offset[0], offset[1], offset[2])
# Add the OpenMOC Lattice to the global collection of all OpenMOC Lattices
OPENMOC_LATTICES[lattice_id] = openmoc_lattice
# Add the OpenCG Lattice to the global collection of all OpenCG Lattices
OPENCG_LATTICES[lattice_id] = opencg_lattice
return openmoc_lattice
def _create_geometry(self):
"""Put a box source in the cube."""
self.input_set.create_materials()
self.input_set.create_geometry()
# Get the root Cell
cells = self.input_set.geometry.getAllCells()
for cell_id in cells:
cell = cells[cell_id]
if cell.getName() == 'root cell':
root_cell = cell
# Apply VACUUM BCs on all bounding surfaces
surfaces = root_cell.getSurfaces()
for surface_id in surfaces:
surface = surfaces[surface_id]._surface
surface.setBoundaryType(openmoc.VACUUM)
# Replace fissionable infinite medium material with C5G7 water
self.materials = \
openmoc.materialize.load_from_hdf5(filename='c5g7-mgxs.h5',
directory='../../sample-input/')
lattice = openmoc.castUniverseToLattice(root_cell.getFillUniverse())
num_x = lattice.getNumX()
num_y = lattice.getNumY()
width_x = lattice.getWidthX()
width_y = lattice.getWidthY()
# Create cells filled with water to put in Lattice
water_cell = openmoc.Cell(name='water')
water_cell.setFill(self.materials['Water'])
water_univ = openmoc.Universe(name='water')
water_univ.addCell(water_cell)
self.source_cell = openmoc.Cell(name='source')
self.source_cell.setFill(self.materials['Water'])
source_univ = openmoc.Universe(name='source')
source_univ.addCell(self.source_cell)
# Create 2D array of Universes in each lattice cell
universes = [[[water_univ]*num_x for _ in range(num_y)]]
# Place fixed source Universe at (x=0.5, y=0.5)
source_x = 0.5
source_y = 0.5
lat_x = (root_cell.getMaxX() - source_x) / width_x
lat_y = (root_cell.getMaxY() - source_y) / width_y
universes[0][int(lat_x)][int(lat_y)] = source_univ
# Create a new Lattice for the Universes
lattice = openmoc.Lattice(name='{0}x{1} lattice'.format(num_x, num_y))
lattice.setWidth(width_x=width_x, width_y=width_y)
lattice.setUniverses(universes)
root_cell.setFill(lattice)
def setUp(self):
self.lattice = openmoc.Lattice(id=12, name="test lattice")
u1 = openmoc.Universe(name='Universe 1')
self.universe = u1
u2 = openmoc.Universe(name='Universe 2')
u3 = openmoc.Universe(name='Universe 3')
self.lattice.setUniverses([[[u1, u2, u1, u2], [u2, u3, u2, u3],
[u1, u2, u1, u2], [u2, u3, u2, u3]],
[[u1, u2, u1, u2], [u2, u3, u2, u3],
[u1, u2, u1, u2], [u2, u3, u2, u3]]])
self.cell = openmoc.Cell(name="test cell")
self.lattice.addCell(self.cell)
def get_openmoc_lattice(opencg_lattice):
if not isinstance(opencg_lattice, opencg.Lattice):
msg = 'Unable to create an OpenMOC Lattice from {0} which ' \
'is not an OpenCG Lattice'.format(opencg_lattice)
raise ValueError(msg)
global OPENMOC_LATTICES
lattice_id = opencg_lattice._id
# If this Lattice was already created, use it
if lattice_id in OPENMOC_LATTICES:
return OPENMOC_LATTICES[lattice_id]
name = opencg_lattice._name
dimension = opencg_lattice._dimension
width = opencg_lattice._width
offset = opencg_lattice._offset
universes = opencg_lattice._universes
# Initialize an empty array for the OpenMOC nested Universes in this Lattice
universe_array = np.ndarray(tuple(np.array(dimension[0:2])), \
dtype=openmoc.Universe)
# Create OpenMOC Universes for each unique nested Universe in this Lattice
unique_universes = opencg_lattice.getUniqueUniverses()
for universe_id, universe in unique_universes.items():
unique_universes[universe_id] = get_openmoc_universe(universe)
# Build the nested Universe array
for y in range(dimension[1]):
for x in range(dimension[0]):
universe_id = universes[0][y][x]._id
universe_array[x][y] = unique_universes[universe_id]
openmoc_lattice = openmoc.Lattice(lattice_id, name)
openmoc_lattice.setWidth(width[0], width[1])
openmoc_lattice.setUniverses(universe_array.tolist())
openmoc_lattice.setOffset(offset[0], offset[1])
# Add the OpenMOC Lattice to the global collection of all OpenMOC Lattices
OPENMOC_LATTICES[lattice_id] = openmoc_lattice
# Add the OpenCG Lattice to the global collection of all OpenCG Lattices
OPENCG_LATTICES[lattice_id] = opencg_lattice
# FIXME
openmoc_lattice.thisown = 0
return openmoc_lattice
def _get_results(self,
num_iters=True,
keff=True,
fluxes=True,
num_fsrs=True,
num_tracks=True,
num_segments=True,
hash_output=True):
"""Digest info from the mesh tallies and return as a string."""
#NOTE Indexing in mesh tally is x,y,z and the mesh is a tuple
# Create OpenMOC Mesh on which to tally fission rates
mesh = openmoc.Mesh(self.solver)
mesh.createLattice(4, 4)
# List reaction rates wanted
rxn_types = OrderedDict({
'flux': openmoc.FLUX_RX,
'total': openmoc.TOTAL_RX,
'fission': openmoc.FISSION_RX,
'nu-fission': openmoc.NUFISSION_RX,
'absorption': openmoc.ABSORPTION_RX
})
# Tally volume-integrated OpenMOC rates on the Mesh
tallies = OrderedDict()
for rxn, rxn_type in rxn_types.items():
tallies[rxn] = mesh.getReactionRates(rxn_types[rxn])
# Test defining a lattice from Python
lattice = openmoc.Lattice()
lattice.setNumX(4)
lattice.setNumY(4)
lattice.setNumZ(1)
lattice.setWidth(10, 10, 1)
lattice.computeSizes()
mesh.setLattice(lattice)
# Tally volume-averaged OpenMOC rates on the Mesh
for rxn, rxn_type in rxn_types.items():
tallies[rxn + "-ave"] = mesh.getReactionRates(rxn_types[rxn], True)
# Append reaction rates to the output string
outstr = ''
for rxn, rates in tallies.items():
outstr += rxn.title() + ' Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in rates]
outstr += '\n'.join(rates) + '\n'
return outstr
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 create_lattice(self):
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')
x0_plane = openmoc.XPlane(x=0)
y0_plane = openmoc.YPlane(y=0)
large_fuel = openmoc.Cell(name='large pin fuel')
large_fuel.setFill(self.materials['UO2'])
large_fuel.addSurface(halfspace=-1, surface=large_zcylinder)
large_moderator = openmoc.Cell(name='large pin moderator')
large_moderator.setFill(self.materials['Water'])
large_moderator.addSurface(halfspace=+1, surface=large_zcylinder)
fuel_quads = [None]*4
mod_quads = [None]*4
for i in range(4):
qname = " (quadrant {})".format(i + 1)
fcell = openmoc.Cell(name='large fuel' + qname)
fcell.setFill(self.materials['UO2'])
fcell.addSurface(halfspace=-1, surface=large_zcylinder)
mcell = openmoc.Cell(name='large mod' + qname)
mcell.setFill(self.materials['Water'])
mcell.addSurface(halfspace=+1, surface=large_zcylinder)
# Add the appropriate quadrants
xspace = 1 if i in (0, 3) else -1
yspace = 1 if i in (0, 1) else -1
fcell.addSurface(halfspace=xspace, surface=x0_plane)
fcell.addSurface(halfspace=yspace, surface=y0_plane)
mcell.addSurface(halfspace=xspace, surface=x0_plane)
mcell.addSurface(halfspace=yspace, surface=y0_plane)
fuel_quads[i] = fcell
mod_quads[i] = mcell
medium_fuel = openmoc.Cell(name='medium pin fuel')
medium_fuel.setFill(self.materials['UO2'])
medium_fuel.addSurface(halfspace=-1, surface=medium_zcylinder)
medium_moderator = openmoc.Cell(name='medium pin moderator')
medium_moderator.setFill(self.materials['Water'])
medium_moderator.addSurface(halfspace=+1, surface=medium_zcylinder)
small_fuel = openmoc.Cell(name='small pin fuel')
small_fuel.setFill(self.materials['UO2'])
small_fuel.addSurface(halfspace=-1, surface=small_zcylinder)
small_moderator = openmoc.Cell(name='small pin moderator')
small_moderator.setFill(self.materials['Water'])
small_moderator.addSurface(halfspace=+1, surface=small_zcylinder)
pin1 = openmoc.Universe(name='large pin cell')
pin2 = openmoc.Universe(name='medium pin cell')
pin3 = openmoc.Universe(name='small pin cell')
pin4 = openmoc.Universe(name='large pin cell (quadrants)')
pin1.addCell(large_fuel)
pin1.addCell(large_moderator)
pin2.addCell(medium_fuel)
pin2.addCell(medium_moderator)
pin3.addCell(small_fuel)
pin3.addCell(small_moderator)
for c in fuel_quads + mod_quads:
pin4.addCell(c)
###################
# SUBDIVIDE PINS #
###################
lleft = [-0.5]*2
uright = [0.5]*2
DIV = (2, 2)
div1 = openmoc.Subdivider(DIV, lleft, uright)
pin1_div = div1.get_subdivided_universe(pin1)
div4 = openmoc.Subdivider(DIV, lleft, uright)
pin4_div = div4.get_subdivided_universe(pin4)
# 2x2 assembly
lattice = openmoc.Lattice(name='2x2 lattice')
lattice.setWidth(width_x=1.0, width_y=1.0)
lattice.setUniverses([[[pin4_div, pin3],
[pin1, pin1_div]]])
return lattice
u5.addCell(cells[9])
u6.addCell(cells[10])
u6.addCell(cells[11])
u7.addCell(assembly1)
u8.addCell(assembly2)
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating 4 x 4 core of 17 x 17 assemblies...')
# 1st 17x17 assembly
a1 = openmoc.Lattice(name='assembly 1')
a1.setWidth(width_x=1.0, width_y=1.0)
a1.setUniverses([[
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
[u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2, u3, u2],
[u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1, u2, u1],
width_y = (root_universe.getMaxY() - root_universe.getMinY()) / num_x
# Create 2D array of Universes in each lattice cell
universes = [[[water_univ]*num_x for _ in range(num_y)]]
# Place fixed source Universe at (x=10, y=10)
source_x = 10
source_y = 10
lat_x = (root_universe.getMaxX() - source_x) / width_x
lat_y = (root_universe.getMaxY() - source_y) / width_y
universes[0][int(lat_x)][int(lat_y)] = source_univ
openmoc.log.py_printf('NORMAL', \
'Creating a {0}x{0} lattice...'.format(num_x, num_y))
lattice = openmoc.Lattice(name='{0}x{1} lattice'.format(num_x, num_y))
lattice.setWidth(width_x=width_x, width_y=width_y)
lattice.setUniverses(universes)
root_cell.setFill(lattice)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
geometry.setRootUniverse(root_universe)
pincell = openmoc.Universe(name='pin cell')
root_universe = openmoc.Universe(name='root universe')
pincell.addCell(fuel)
pincell.addCell(moderator)
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating simple 2 x 2 lattice...')
lattice = openmoc.Lattice(name='2x2 lattice')
lattice.setWidth(width_x=2.0, width_y=2.0)
lattice.setUniverses([[[pincell, pincell], [pincell, pincell]]])
root_cell.setFill(lattice)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
geometry.setRootUniverse(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)
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating simple 4 x 4 lattice...')
lattice = openmoc.Lattice(name='4x4 lattice')
lattice.setWidth(width_x=1.0, width_y=1.0)
lattice.setUniverses([[[pin1, pin2, pin1, pin2],
[pin2, pin3, pin2, pin3],
[pin1, pin2, pin1, pin2],
[pin2, pin3, pin2, pin3]]])
root_cell.setFill(lattice)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
root_cell.addSurface(-1, boundaries[2])
root_cell.addSurface(+1, boundaries[3])
root_universe = openmoc.Universe(name='Root Universe')
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating lattices...')
lattices = list()
# Top left, bottom right 17 x 17 assemblies
lattices.append(openmoc.Lattice(name='Assembly 1'))
lattices[-1].setWidth(width_x=1.26, width_y=1.26)
template = [[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 1, 1, 1],
[1, 1, 1, 2, 1, 1, 1, 1, 1, 1, 1, 1, 1, 2, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 2, 1, 1, 2, 1, 1, 3, 1, 1, 2, 1, 1, 2, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 2, 1, 1, 1, 1, 1, 1, 1, 1, 1, 2, 1, 1, 1],
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 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 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 get_openmoc_lattice(openmc_lattice):
"""Return an OpenMOC lattice corresponding to an OpenMOC lattice.
Parameters
----------
openmc_lattice : openmc.RectLattice
OpenMC lattice
Returns
-------
openmoc_lattice : openmoc.Lattice
Equivalent OpenMOC lattice
"""
cv.check_type('openmc_lattice', openmc_lattice, openmc.RectLattice)
lattice_id = openmc_lattice.id
# If this Lattice was already created, use it
if lattice_id in OPENMOC_LATTICES:
return OPENMOC_LATTICES[lattice_id]
# Create an OpenMOC Lattice to represent this OpenMC Lattice
name = openmc_lattice.name
dimension = openmc_lattice.shape
pitch = openmc_lattice.pitch
lower_left = openmc_lattice.lower_left
universes = openmc_lattice.universes
# Convert 2D dimension to 3D for OpenMOC
if len(dimension) == 2:
new_dimension = np.ones(3, dtype=int)
new_dimension[:2] = dimension
dimension = new_dimension
# Convert 2D pitch to 3D for OpenMOC
if len(pitch) == 2:
new_pitch = np.ones(3, dtype=np.float64) * np.finfo(np.float64).max
new_pitch[:2] = pitch
pitch = new_pitch
# Convert 2D lower left to 3D for OpenMOC
if len(lower_left) == 2:
new_lower_left = np.ones(3, dtype=np.float64)
new_lower_left *= np.finfo(np.float64).min / 2.
new_lower_left[:2] = lower_left
lower_left = new_lower_left
# Convert 2D universes array to 3D for OpenMOC
if len(universes.shape) == 2:
new_universes = universes.copy()
new_universes.shape = (1,) + universes.shape
universes = new_universes
# Initialize an empty array for the OpenMOC nested Universes in this Lattice
universe_array = np.ndarray(tuple(dimension[::-1]), dtype=openmoc.Universe)
# Create OpenMOC Universes for each unique nested Universe in this Lattice
unique_universes = openmc_lattice.get_unique_universes()
for universe_id, universe in unique_universes.items():
unique_universes[universe_id] = get_openmoc_universe(universe)
# Build the nested Universe array
for z in range(dimension[2]):
for y in range(dimension[1]):
for x in range(dimension[0]):
universe_id = universes[z][y][x].id
universe_array[z][y][x] = unique_universes[universe_id]
openmoc_lattice = openmoc.Lattice(lattice_id, name)
openmoc_lattice.setWidth(pitch[0], pitch[1], pitch[2])
openmoc_lattice.setUniverses(universe_array.tolist())
offset = np.array(lower_left, dtype=np.float64) - \
((np.array(pitch, dtype=np.float64) *
np.array(dimension, dtype=np.float64))) / -2.0
openmoc_lattice.setOffset(offset[0], offset[1], offset[2])
# Add the OpenMC Lattice to the global collection of all OpenMC Lattices
OPENMC_LATTICES[lattice_id] = openmc_lattice
# Add the OpenMOC Lattice to the global collection of all OpenMOC Lattices
OPENMOC_LATTICES[lattice_id] = openmoc_lattice
return openmoc_lattice
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()
pin = openmoc.Universe(name='pin cell')
root_universe = openmoc.Universe(name='root universe')
pin.addCell(fuel)
pin.addCell(moderator)
pin.addCell(grid_spacer)
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating 4 x 4 lattice w/ grid spacers...')
lattice = openmoc.Lattice(name='4x4 lattice w/ grid spacers')
lattice.setWidth(width_x=1.0, width_y=1.0)
lattice.setUniverses([[[pin, pin, pin, pin], [pin, pin, pin, pin],
[pin, pin, pin, pin], [pin, pin, pin, pin]]])
root_cell.setFill(lattice)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
geometry = openmoc.Geometry()
geometry.setRootUniverse(root_universe)
###############################################################################
import openmoc
from universes import universes, cells
###############################################################################
########################### Creating Lattices #############################
###############################################################################
# The number of uniform refinements to perform on the assembly lattices
refines = 10
lattices = {}
# Instantiate Lattices
lattices['Region 1 Assembly'] = openmoc.Lattice()
lattices['Region 2 Assembly'] = openmoc.Lattice()
lattices['Region 3 Assembly'] = openmoc.Lattice()
lattices['Region 4 Assembly'] = openmoc.Lattice()
lattices['Region 5 Assembly'] = openmoc.Lattice()
lattices['Root'] = openmoc.Lattice()
u1 = universes['Region 1']
u2 = universes['Region 2']
u3 = universes['Region 3']
u4 = universes['Region 4']
u5 = universes['Region 5']
lattices['Region 1 Assembly'].setWidth(15.0/refines, 15.0/refines)
lattices['Region 1 Assembly'].setUniverses([[[u1] * refines] * refines])
lattices['Region 2 Assembly'].setWidth(15.0/refines, 15.0/refines)
lattices['Region 2 Assembly'].setUniverses([[[u2] * refines] * refines])
root_cell.addSurface(halfspace=+1, surface=left) root_cell.addSurface(halfspace=-1, surface=right) root_cell.addSurface(halfspace=+1, surface=bottom) root_cell.addSurface(halfspace=-1, surface=top) ############################################################################# ########################## Creating Universes ########################## ############################################################################# fill_universe = openmoc.Universe(name='homogeneous fill cell') fill_universe.addCell(fill) root_universe = openmoc.Universe(name='root universe') root_universe.addCell(root_cell) ############################################################################# ########################### Creating Lattices ########################## ############################################################################# 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) ############################################################################# ######################### Creating the Geometry ######################### ############################################################################# geometry = openmoc.Geometry() geometry.setRootUniverse(root_universe)
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()
root_cell.addSurface(halfspace=+1, surface=left)
root_cell.addSurface(halfspace=-1, surface=right)
root_cell.addSurface(halfspace=+1, surface=bottom)
root_cell.addSurface(halfspace=-1, surface=top)
root_universe = openmoc.Universe(name='root universe')
root_universe.addCell(root_cell)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating LRA lattices...')
# Assembly 1
assembly1_lattice = openmoc.Lattice(name='assembly 1')
assembly1_lattice.setWidth(width_x=1.5, width_y=1.5)
template = [[region1] * 10] * 10
assembly1_lattice.setUniverses([template])
assembly1_cell.setFill(assembly1_lattice)
# Assembly 2
assembly2_lattice = openmoc.Lattice(name='assembly 2')
assembly2_lattice.setWidth(width_x=1.5, width_y=1.5)
template = [[region2] * 10] * 10
assembly2_lattice.setUniverses([template])
assembly2_cell.setFill(assembly2_lattice)
# Assembly 3
assembly3_lattice = openmoc.Lattice(name='assembly 3')
assembly3_lattice.setWidth(width_x=1.5, width_y=1.5)
from surfaces import gap
###############################################################################
######################### Set Simulation Param ############################
###############################################################################
reflector_refines = 3
###############################################################################
########################### Creating Lattices #############################
###############################################################################
lattices = {}
# Instantiate Lattices
lattices['Refined Reflector Mesh'] = openmoc.Lattice()
lattices['Reflector Unrodded Assembly'] = openmoc.Lattice()
lattices['Reflector Rodded Assembly'] = openmoc.Lattice()
lattices['Reflector Right Assembly'] = openmoc.Lattice()
lattices['Reflector Bottom Assembly'] = openmoc.Lattice()
lattices['Reflector Corner Assembly'] = openmoc.Lattice()
lattices['Reflector Assembly'] = openmoc.Lattice()
lattices['UO2 Unrodded Assembly'] = openmoc.Lattice()
lattices['UO2 Rodded Assembly'] = openmoc.Lattice()
lattices['MOX Unrodded Assembly'] = openmoc.Lattice()
lattices['MOX Rodded Assembly'] = openmoc.Lattice()
lattices['Root'] = openmoc.Lattice()
lattices['Gap Reflector Rodded Assembly'] = openmoc.Lattice()
lattices['Gap Reflector Right Assembly'] = openmoc.Lattice()
lattices['Gap Reflector Bottom Assembly'] = openmoc.Lattice()
import openmoc
from universes import universes, cells
###############################################################################
########################### Creating Lattices #############################
###############################################################################
lattices = {}
# Instantiate Lattices
lattices['Root'] = openmoc.Lattice()
# Fill cells with lattices
cells['Root'].setFill(lattices['Root'])
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)
###############################################################################
# Creating Lattices
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating nested 2 x 2 lattices...')
# 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)
###############################################################################
# Creating the Geometry
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating geometry...')
root_cell.addSurface(halfspace=+1, surface=zmin)
root_cell.addSurface(halfspace=-1, surface=zmax)
root_universe = openmoc.Universe(name='Root Universe')
root_universe.addCell(root_cell)
###############################################################################
########################### Creating Lattices #############################
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating lattices...')
lattices = list()
# Sliced up water cells - semi finely spaced
lattices.append(openmoc.Lattice(name='Semi-Finely Spaced Reflector'))
lattices[-1].setWidth(width_x=0.126, width_y=0.126)
template = [[reflector] * 10] * 10
lattices[-1].setUniverses([template])
refined_reflector_cell.setFill(lattices[-1])
# UO2 unrodded 17 x 17 assemblies
lattices.append(openmoc.Lattice(name='Assembly UO2 Unrodded'))
lattices[-1].setWidth(width_x=1.26, width_y=1.26)
template = [[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 1, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 1, 1, 1],
[1, 1, 1, 2, 1, 1, 1, 1, 1, 1, 1, 1, 1, 2, 1, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
[1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1, 2, 1, 1],
[1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1, 1],
