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 test_ids(self):
openmoc.reset_material_id()
material_2 = openmoc.Cell()
self.assertEqual(material_2.getId(), 1000000)
openmoc.maximize_material_id(10000000)
material_3 = openmoc.Cell()
self.assertEqual(material_3.getId(), 1000001)
self.test_material.printString()
def test_ids(self):
openmoc.reset_cell_id()
cell_2 = openmoc.Cell()
self.assertEqual(cell_2.getId(), 1000000)
openmoc.maximize_cell_id(10000000)
cell_3 = openmoc.Cell()
self.assertEqual(cell_3.getId(), 10000000)
self.cell.printString()
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 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 __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 setRootUniverse(self, boundary):
# Root Cell
self.root_cell = openmoc.Cell(name='Full Geometry')
self.root_cell.setFill(self.assembly)
self.root_cell.setRegion(boundary)
# Root Universe
self.root_universe = openmoc.Universe(name='Root Universe')
self.root_universe.addCell(self.root_cell)
def get_openmoc_cell(opencg_cell):
"""Return an OpenMOC cell corresponding to an OpenCG cell.
Parameters
----------
opencg_cell : opencg.Cell
OpenCG cell
Returns
-------
openmoc_cell : openmoc.Cell
Equivalent OpenMOC cell
"""
cv.check_type('openmoc_cell', opencg_cell, opencg.Cell)
global OPENMOC_CELLS
cell_id = opencg_cell.id
# If this Cell was already created, use it
if cell_id in OPENMOC_CELLS:
return OPENMOC_CELLS[cell_id]
# Create an OpenMOC Cell to represent this OpenCG Cell
name = str(opencg_cell.name)
openmoc_cell = openmoc.Cell(cell_id, name)
fill = opencg_cell.fill
if opencg_cell.type == 'universe':
openmoc_cell.setFill(get_openmoc_universe(fill))
elif opencg_cell.type == 'lattice':
openmoc_cell.setFill(get_openmoc_lattice(fill))
else:
openmoc_cell.setFill(get_openmoc_material(fill))
if opencg_cell.rotation is not None:
rotation = np.asarray(opencg_cell.rotation, dtype=np.float64)
openmoc_cell.setRotation(rotation)
if opencg_cell.translation is not None:
translation = np.asarray(opencg_cell.translation, dtype=np.float64)
openmoc_cell.setTranslation(translation)
surfaces = opencg_cell.surfaces
for surface_id in surfaces:
surface = surfaces[surface_id][0]
halfspace = int(surfaces[surface_id][1])
openmoc_cell.addSurface(halfspace, get_openmoc_surface(surface))
# Add the OpenMOC Cell to the global collection of all OpenMOC Cells
OPENMOC_CELLS[cell_id] = openmoc_cell
# Add the OpenCG Cell to the global collection of all OpenCG Cells
OPENCG_CELLS[cell_id] = opencg_cell
return openmoc_cell
def _to_openmoc_universe(self, name=""):
if name:
mesh_name = "x".join(np.array(self.division, dtype=str))
name += " (subdivided " + mesh_name + ")"
uout = openmoc.Universe(name=name)
cout = openmoc.Cell()
cout.setFill(self)
uout.addCell(cout)
return uout
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_cell(openmc_cell):
"""Return an OpenMOC cell corresponding to an OpenMC cell.
Parameters
----------
openmc_cell : openmc.Cell
OpenMC cell
Returns
-------
openmoc_cell : openmoc.Cell
Equivalent OpenMOC cell
"""
cv.check_type('openmc_cell', openmc_cell, openmc.Cell)
cell_id = openmc_cell.id
# If this Cell was already created, use it
if cell_id in OPENMOC_CELLS:
return OPENMOC_CELLS[cell_id]
# Create an OpenMOC Cell to represent this OpenMC Cell
name = openmc_cell.name
openmoc_cell = openmoc.Cell(cell_id, name)
fill = openmc_cell.fill
if openmc_cell.fill_type == 'material':
openmoc_cell.setFill(get_openmoc_material(fill))
elif openmc_cell.fill_type == 'universe':
openmoc_cell.setFill(get_openmoc_universe(fill))
else:
openmoc_cell.setFill(get_openmoc_lattice(fill))
if openmc_cell.rotation is not None:
rotation = np.asarray(openmc_cell.rotation, dtype=np.float64)
openmoc_cell.setRotation(rotation)
if openmc_cell.translation is not None:
translation = np.asarray(openmc_cell.translation, dtype=np.float64)
openmoc_cell.setTranslation(translation)
# Convert OpenMC's cell region to an equivalent OpenMOC region
if openmc_cell.region is not None:
openmoc_cell.setRegion(get_openmoc_region(openmc_cell.region))
# Add the OpenMC Cell to the global collection of all OpenMC Cells
OPENMC_CELLS[cell_id] = openmc_cell
# Add the OpenMOC Cell to the global collection of all OpenMOC Cells
OPENMOC_CELLS[cell_id] = openmoc_cell
return openmoc_cell
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_cell(opencg_cell):
if not isinstance(opencg_cell, opencg.Cell):
msg = 'Unable to create an OpenMOC Cell from {0} which ' \
'is not an OpenCG Cell'.format(opencg_cell)
raise ValueError(msg)
global OPENMOC_CELLS
cell_id = opencg_cell._id
# If this Cell was already created, use it
if cell_id in OPENMOC_CELLS:
return OPENMOC_CELLS[cell_id]
# Create an OpenMOC Cell to represent this OpenCG Cell
name = opencg_cell._name
fill = opencg_cell._fill
openmoc_cell = openmoc.Cell(cell_id, name)
if opencg_cell._type == 'universe':
openmoc_cell.setFill(get_openmoc_universe(fill))
elif opencg_cell._type == 'lattice':
openmoc_cell.setFill(get_openmoc_lattice(fill))
else:
openmoc_cell.setFill(get_openmoc_material(fill))
surfaces = opencg_cell._surfaces
for surface_id in surfaces:
surface = surfaces[surface_id][0]
halfspace = int(surfaces[surface_id][1])
openmoc_cell.addSurface(halfspace, get_openmoc_surface(surface))
# Add the OpenMOC Cell to the global collection of all OpenMOC Cells
OPENMOC_CELLS[cell_id] = openmoc_cell
# Add the OpenCG Cell to the global collection of all OpenCG Cells
OPENCG_CELLS[cell_id] = opencg_cell
# FIXME
openmoc_cell.thisown = 0
return openmoc_cell
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 _subdivide2d(self, target):
nx, ny = self.division
dx, dy = self.deltas
x0 = nx * dx / 2
y0 = -ny * dy / 2
universes = [[None for _ in range(nx)] for _ in range(ny)]
# for 2D, no translation in z
tz = 0
for j in range(ny):
# translation in y
ty = y0 + dy * (j + .5)
for i in range(nx):
# translation in x
tx = x0 - dx * (i + .5)
t_vector = np.array([tx, ty, tz])
cell = openmoc.Cell()
cell.setFill(target)
cell.setTranslation(t_vector)
univ = openmoc.Universe()
univ.addCell(cell)
universes[j][i] = univ
self.setUniverses([universes])
return self._to_openmoc_universe(name=target.getName())
zmax.setBoundaryType(openmoc.REFLECTIVE)
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')
###############################################################################
############################# Creating Cells ##############################
###############################################################################
log.py_printf('NORMAL', 'Creating cells...')
large_fuel = openmoc.Cell()
large_fuel.setFill(materials['UO2'])
large_fuel.addSurface(halfspace=-1, surface=large_zcylinder)
large_moderator = openmoc.Cell()
large_moderator.setFill(materials['Water'])
large_moderator.addSurface(halfspace=+1, surface=large_zcylinder)
medium_fuel = openmoc.Cell()
medium_fuel.setFill(materials['UO2'])
medium_fuel.addSurface(halfspace=-1, surface=medium_zcylinder)
medium_moderator = openmoc.Cell()
medium_moderator.setFill(materials['Water'])
medium_moderator.addSurface(halfspace=+1, surface=medium_zcylinder)
def setUp(self):
self.cell = openmoc.Cell(id=12, name="test cell")
num_sectors = 4
###############################################################################
########################### Creating Materials ############################
###############################################################################
materials = materialize.load_from_hdf5('c5g7-mgxs.h5', '../../')
###############################################################################
###################### Creating Cells and Universes #######################
###############################################################################
cells = {}
# Instantiate Cells
cells['Root'] = openmoc.Cell()
cells['Gap Root'] = openmoc.Cell()
cells['UO2'] = openmoc.Cell()
cells['MOX 4.3%'] = openmoc.Cell()
cells['MOX 7.0%'] = openmoc.Cell()
cells['MOX 8.7%'] = openmoc.Cell()
cells['Guide Tube'] = openmoc.Cell()
cells['Fission Chamber'] = openmoc.Cell()
cells['Control Rod'] = openmoc.Cell()
cells['Moderator'] = openmoc.Cell()
cells['Reflector'] = openmoc.Cell()
cells['Moderator in Pin'] = openmoc.Cell()
cells['Refined Reflector Pin'] = openmoc.Cell()
cells['Refined Reflector Mesh'] = openmoc.Cell()
cells['UO2 Unrodded Assembly'] = openmoc.Cell()
cells['UO2 Rodded Assembly'] = openmoc.Cell()
right = openmoc.XPlane(x=2.0, name='right')
top = openmoc.YPlane(y=2.0, name='top')
bottom = openmoc.YPlane(y=-2.0, name='bottom')
left.setBoundaryType(openmoc.REFLECTIVE)
right.setBoundaryType(openmoc.REFLECTIVE)
top.setBoundaryType(openmoc.REFLECTIVE)
bottom.setBoundaryType(openmoc.REFLECTIVE)
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
fuel = openmoc.Cell(name='fuel')
fuel.setFill(materials['UO2'])
fuel.addSurface(halfspace=-1, surface=zcylinder)
moderator = openmoc.Cell(name='moderator')
moderator.setFill(materials['Water'])
moderator.addSurface(halfspace=+1, surface=zcylinder)
moderator.addSurface(halfspace=+1, surface=left)
moderator.addSurface(halfspace=-1, surface=right)
moderator.addSurface(halfspace=+1, surface=bottom)
moderator.addSurface(halfspace=-1, surface=top)
###############################################################################
# Creating Universes
###############################################################################
left = openmoc.XPlane(x=-20.0, name='left')
right = openmoc.XPlane(x=20.0, name='right')
top = openmoc.YPlane(y=20.0, name='top')
bottom = openmoc.YPlane(y=-20.0, name='bottom')
boundaries = [left, right, top, bottom]
for boundary in boundaries: boundary.setBoundaryType(openmoc.VACUUM)
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
water_cell = openmoc.Cell(name='water')
water_cell.setFill(materials['Water'])
source_cell = openmoc.Cell(name='source')
source_cell.setFill(materials['Water'])
root_cell = openmoc.Cell(name='root cell')
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
###############################################################################
boundaries = [left, right, top, bottom]
for boundary in boundaries: boundary.setBoundaryType(openmoc.REFLECTIVE)
zcylinders = list()
radii = [0.15, 0.2, 0.25, 0.3, 0.35, 0.4]
for r in radii: zcylinders.append(openmoc.ZCylinder(x=0.0, y=0.0, radius=r))
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
# Create a list of 12 Cell instances
cells = [openmoc.Cell() for i in range(12)]
# Append 3 CellFills for the assemblies and full core
assembly1 = openmoc.Cell(name='assembly 1')
assembly2 = openmoc.Cell(name='assembly 2')
root_cell = openmoc.Cell(name='full core')
# Create fuel/moderator by adding the appropriate Surfaces and Materials
cells[0].addSurface(halfspace=-1, surface=zcylinders[0])
cells[1].addSurface(halfspace=+1, surface=zcylinders[0])
cells[2].addSurface(halfspace=-1, surface=zcylinders[1])
cells[3].addSurface(halfspace=+1, surface=zcylinders[1])
cells[4].addSurface(halfspace=-1, surface=zcylinders[2])
cells[5].addSurface(halfspace=+1, surface=zcylinders[2])
cells[6].addSurface(halfspace=-1, surface=zcylinders[3])
cells[7].addSurface(halfspace=+1, surface=zcylinders[3])
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()
import openmoc.materialize as materialize
###############################################################################
# Creating Materials
###############################################################################
materials = openmoc.materialize.load_from_hdf5('LRA-mgxs.h5', './')
###############################################################################
# Create dictionary of all cells
###############################################################################
cells = {}
# Instantiate Cells
cells['Region 1'] = openmoc.Cell(name='Region 1')
cells['Region 2'] = openmoc.Cell(name='Region 2')
cells['Region 3'] = openmoc.Cell(name='Region 3')
cells['Region 4'] = openmoc.Cell(name='Region 4')
cells['Region 5'] = openmoc.Cell(name='Region 5')
cells['Region 1 Assembly'] = openmoc.Cell(name='Region 1 Assembly')
cells['Region 2 Assembly'] = openmoc.Cell(name='Region 2 Assembly')
cells['Region 3 Assembly'] = openmoc.Cell(name='Region 3 Assembly')
cells['Region 4 Assembly'] = openmoc.Cell(name='Region 4 Assembly')
cells['Region 5 Assembly'] = openmoc.Cell(name='Region 5 Assembly')
cells['Root'] = openmoc.Cell(name='Root')
# Register Materials with Cells
cells['Region 1'].setFill(materials['Region 1'])
cells['Region 2'].setFill(materials['Region 2'])
cells['Region 3'].setFill(materials['Region 3'])
right = openmoc.XPlane(x=100.0, name='right')
top = openmoc.YPlane(y=100.0, name='top')
bottom = openmoc.YPlane(y=-100.0, name='bottom')
left.setBoundaryType(openmoc.REFLECTIVE)
right.setBoundaryType(openmoc.REFLECTIVE)
top.setBoundaryType(openmoc.REFLECTIVE)
bottom.setBoundaryType(openmoc.REFLECTIVE)
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
cell = openmoc.Cell()
cell.setFill(infinite_medium)
cell.addSurface(halfspace=+1, surface=left)
cell.addSurface(halfspace=-1, surface=right)
cell.addSurface(halfspace=+1, surface=bottom)
cell.addSurface(halfspace=-1, surface=top)
###############################################################################
# Creating Universes
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating universes...')
root_universe = openmoc.Universe(name='root universe')
root_universe.addCell(cell)
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")
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)
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
large_fuel = openmoc.Cell(name='large pin fuel')
large_fuel.setNumRings(3)
large_fuel.setNumSectors(8)
large_fuel.setFill(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(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(materials['UO2'])
medium_fuel.addSurface(halfspace=-1, surface=medium_zcylinder)
right = openmoc.XPlane(x=82.5)
bottom = openmoc.YPlane(y=-82.5)
top = openmoc.YPlane(y=82.5)
left.setBoundaryType(openmoc.REFLECTIVE)
right.setBoundaryType(openmoc.VACUUM)
bottom.setBoundaryType(openmoc.REFLECTIVE)
top.setBoundaryType(openmoc.VACUUM)
###############################################################################
# Creating Cells and Universes
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating cells...')
# Region 1
region1_cell = openmoc.Cell(name='region 1')
region1_cell.setFill(materials['region_1'])
region1 = openmoc.Universe(name='region 1')
region1.addCell(region1_cell)
# Region 2
region2_cell = openmoc.Cell(name='region 2')
region2_cell.setFill(materials['region_2'])
region2 = openmoc.Universe(name='region 2')
region2.addCell(region2_cell)
# Region 3
region3_cell = openmoc.Cell(name='region 3')
region3_cell.setFill(materials['region_3'])
region3 = openmoc.Universe(name='region 3')
region3.addCell(region3_cell)
def _run_openmoc(self):
openmoc.set_log_level('NORMAL')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.XPlane(-40.)
s2 = openmoc.XPlane(-50.)
s3 = openmoc.XPlane(-60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(+1, s1)
c2.addSurface(+1, s2)
c2.addSurface(+1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMinXBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MinX: %f', u.getMinX())
py_printf('NORMAL', 'MinXBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.YPlane(-40.)
s2 = openmoc.YPlane(-50.)
s3 = openmoc.YPlane(-60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(+1, s1)
c2.addSurface(+1, s2)
c2.addSurface(+1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMinYBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MinY: %f', u.getMinY())
py_printf('NORMAL', 'MinYBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.ZPlane(-40.)
s2 = openmoc.ZPlane(-50.)
s3 = openmoc.ZPlane(-60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(+1, s1)
c2.addSurface(+1, s2)
c2.addSurface(+1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMinZBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MinZ: %f', u.getMinZ())
py_printf('NORMAL', 'MinZBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.XPlane(40.)
s2 = openmoc.XPlane(50.)
s3 = openmoc.XPlane(60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(-1, s1)
c2.addSurface(-1, s2)
c2.addSurface(-1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMaxXBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MaxX: %f', u.getMaxX())
py_printf('NORMAL', 'MaxXBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.YPlane(40.)
s2 = openmoc.YPlane(50.)
s3 = openmoc.YPlane(60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(-1, s1)
c2.addSurface(-1, s2)
c2.addSurface(-1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMaxYBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MaxY: %f', u.getMaxY())
py_printf('NORMAL', 'MaxYBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
c1 = openmoc.Cell()
c2 = openmoc.Cell()
s1 = openmoc.ZPlane(40.)
s2 = openmoc.ZPlane(50.)
s3 = openmoc.ZPlane(60.)
s1.setBoundaryType(openmoc.VACUUM)
s2.setBoundaryType(openmoc.PERIODIC)
s3.setBoundaryType(openmoc.REFLECTIVE)
c1.addSurface(-1, s1)
c2.addSurface(-1, s2)
c2.addSurface(-1, s3)
u = openmoc.Universe()
u.addCell(c1)
u.addCell(c2)
boundary = u.getMaxZBoundaryType()
if boundary == 0:
boundary = 'VACUUM'
elif boundary == 1:
boundary = 'REFLECTIVE'
elif boundary == 2:
boundary = 'PERIODIC'
else:
boundary = 'BOUNDARY_NONE'
py_printf('NORMAL', 'MaxZ: %f', u.getMaxZ())
py_printf('NORMAL', 'MaxZBoundaryType: %s', boundary)
py_printf('SEPARATOR', '')
sW = openmoc.XPlane(10)
sE = openmoc.XPlane(20)
sS = openmoc.YPlane(30)
sN = openmoc.YPlane(40)
sB = openmoc.ZPlane(50)
sT = openmoc.ZPlane(60)
sW.setBoundaryType(openmoc.VACUUM)
sE.setBoundaryType(openmoc.REFLECTIVE)
sS.setBoundaryType(openmoc.VACUUM)
sN.setBoundaryType(openmoc.REFLECTIVE)
sB.setBoundaryType(openmoc.PERIODIC)
sT.setBoundaryType(openmoc.REFLECTIVE)
sX_mid = openmoc.XPlane(15)
sY_mid = openmoc.YPlane(35)
sZ_mid = openmoc.ZPlane(55)
sX_mid.setBoundaryType(openmoc.BOUNDARY_NONE)
sY_mid.setBoundaryType(openmoc.BOUNDARY_NONE)
sZ_mid.setBoundaryType(openmoc.BOUNDARY_NONE)
cell = openmoc.Cell()
cell.addSurface(+1, sW)
cell.addSurface(-1, sE)
cell.addSurface(+1, sS)
cell.addSurface(-1, sN)
cell.addSurface(+1, sB)
cell.addSurface(-1, sT)
cell.addSurface(+1, sX_mid)
cell.addSurface(-1, sX_mid)
cell.addSurface(+1, sY_mid)
cell.addSurface(-1, sY_mid)
cell.addSurface(+1, sZ_mid)
cell.addSurface(-1, sZ_mid)
univ = openmoc.Universe()
univ.addCell(cell)
py_printf('NORMAL', 'MinX: %f', univ.getMinX())
py_printf('NORMAL', 'MinXBoundaryType: %s', univ.getMinXBoundaryType())
py_printf('NORMAL', 'MinY: %f', univ.getMinY())
py_printf('NORMAL', 'MinYBoundaryType: %s', univ.getMinYBoundaryType())
py_printf('NORMAL', 'MinZ: %f', univ.getMinZ())
py_printf('NORMAL', 'MinZBoundaryType: %s', univ.getMinZBoundaryType())
py_printf('NORMAL', 'MaxX: %f', univ.getMaxX())
py_printf('NORMAL', 'MaxXBoundaryType: %s', univ.getMaxXBoundaryType())
py_printf('NORMAL', 'MaxY: %f', univ.getMaxY())
py_printf('NORMAL', 'MaxYBoundaryType: %s', univ.getMaxYBoundaryType())
py_printf('NORMAL', 'MaxZ: %f', univ.getMaxZ())
py_printf('NORMAL', 'MaxZBoundaryType: %s', univ.getMaxZBoundaryType())
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)
