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_intersection(self):
intersection = openmoc.Intersection()
# Define surfaces
p1x = openmoc.XPlane(x=3)
p2x = openmoc.XPlane(x=-2)
p1y = openmoc.YPlane(y=1)
p2y = openmoc.YPlane(y=-0.5)
p1z = openmoc.ZPlane(z=8)
p2z = openmoc.ZPlane(z=-4)
# Define boundary types
p1x.setBoundaryType(openmoc.VACUUM)
p2x.setBoundaryType(openmoc.REFLECTIVE)
p1y.setBoundaryType(openmoc.PERIODIC)
p2y.setBoundaryType(openmoc.REFLECTIVE)
p1z.setBoundaryType(openmoc.PERIODIC)
p2z.setBoundaryType(openmoc.VACUUM)
# Define halfspaces
h1x = openmoc.Halfspace(-1, p1x)
h2x = openmoc.Halfspace(+1, p2x)
h1y = openmoc.Halfspace(-1, p1y)
h2y = openmoc.Halfspace(+1, p2y)
h1z = openmoc.Halfspace(-1, p1z)
h2z = openmoc.Halfspace(+1, p2z)
# Add halfspaces
intersection.addNode(h1x)
intersection.addNode(h2x)
intersection.addNode(h1y)
intersection.addNode(h2y)
intersection.addNode(h1z)
intersection.addNode(h2z)
# Test getMaxXYZ + MaxXYZboundary
self.assertEqual(intersection.getMaxX(), 3)
self.assertEqual(intersection.getMaxXBoundaryType(), openmoc.VACUUM)
self.assertEqual(intersection.getMaxY(), 1)
self.assertEqual(intersection.getMaxYBoundaryType(), openmoc.PERIODIC)
self.assertEqual(intersection.getMaxZ(), 8)
self.assertEqual(intersection.getMaxZBoundaryType(), openmoc.PERIODIC)
# Test getMinXYZ + MinXYZboundary
self.assertEqual(intersection.getMinX(), -2)
self.assertEqual(intersection.getMinXBoundaryType(),
openmoc.REFLECTIVE)
self.assertEqual(intersection.getMinY(), -0.5)
self.assertEqual(intersection.getMinYBoundaryType(),
openmoc.REFLECTIVE)
self.assertEqual(intersection.getMinZ(), -4)
self.assertEqual(intersection.getMinZBoundaryType(), openmoc.VACUUM)
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_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()
basic_material = openmoc.Material(name='1-group infinite medium') basic_material.setNumEnergyGroups(1) basic_material.setSigmaF([0.0414198575]) basic_material.setNuSigmaF([0.0994076580]) basic_material.setSigmaS([0.383259177]) basic_material.setChi([1.0]) basic_material.setSigmaT([0.452648699]) ############################################################################# ########################## Creating Surfaces ############################ ############################################################################# left = openmoc.XPlane(x=-length / 2, name='left') right = openmoc.XPlane(x=length / 2, name='right') top = openmoc.YPlane(y=length / 2, name='top') bottom = openmoc.YPlane(y=-length / 2, name='bottom') left.setBoundaryType(openmoc.REFLECTIVE) right.setBoundaryType(openmoc.REFLECTIVE) top.setBoundaryType(openmoc.REFLECTIVE) bottom.setBoundaryType(openmoc.REFLECTIVE) ############################################################################# ############################ Creating Cells ############################# ############################################################################# fill = openmoc.Cell(name='fill') fill.setFill(basic_material) root_cell = openmoc.Cell(name='root cell')
def test_complement(self):
complement = openmoc.Complement()
intersection = openmoc.Intersection()
# Define surfaces
p1x = openmoc.XPlane(x=3)
p2x = openmoc.XPlane(x=-2)
p1y = openmoc.YPlane(y=1)
p2y = openmoc.YPlane(y=-0.5)
p1z = openmoc.ZPlane(z=8)
p2z = openmoc.ZPlane(z=-4)
# Define boundary types
p1x.setBoundaryType(openmoc.VACUUM)
p2x.setBoundaryType(openmoc.REFLECTIVE)
p1y.setBoundaryType(openmoc.PERIODIC)
p2y.setBoundaryType(openmoc.REFLECTIVE)
p1z.setBoundaryType(openmoc.PERIODIC)
p2z.setBoundaryType(openmoc.VACUUM)
# Define halfspaces
h1x = openmoc.Halfspace(-1, p1x)
h2x = openmoc.Halfspace(+1, p2x)
h1y = openmoc.Halfspace(-1, p1y)
h2y = openmoc.Halfspace(+1, p2y)
h1z = openmoc.Halfspace(-1, p1z)
h2z = openmoc.Halfspace(+1, p2z)
# Add halfspaces
intersection.addNode(h1x)
intersection.addNode(h2x)
intersection.addNode(h1y)
intersection.addNode(h2y)
intersection.addNode(h1z)
intersection.addNode(h2z)
complement.addNode(intersection)
# Test getMaxXYZ + MaxXYZboundary
#FIXME Implement boundary type getter for complement regions
self.assertEqual(complement.getMaxX(), 3)
with self.assertRaises(Exception):
self.assertEqual(complement.getMaxXBoundaryType(), openmoc.VACUUM)
self.assertEqual(complement.getMaxY(), 1)
with self.assertRaises(Exception):
self.assertEqual(complement.getMaxYBoundaryType(),
openmoc.PERIODIC)
self.assertEqual(complement.getMaxZ(), 8)
with self.assertRaises(Exception):
self.assertEqual(complement.getMaxZBoundaryType(),
openmoc.PERIODIC)
# Test getMinXYZ + MinXYZboundary
self.assertEqual(complement.getMinX(), -2)
with self.assertRaises(Exception):
self.assertEqual(complement.getMinXBoundaryType(),
openmoc.REFLECTIVE)
self.assertEqual(complement.getMinY(), -0.5)
with self.assertRaises(Exception):
self.assertEqual(complement.getMinYBoundaryType(),
openmoc.REFLECTIVE)
self.assertEqual(complement.getMinZ(), -4)
with self.assertRaises(Exception):
self.assertEqual(complement.getMinZBoundaryType(), openmoc.VACUUM)
def test_union(self):
union = openmoc.Union()
# Define surfaces
p1x = openmoc.XPlane(x=3)
p2x = openmoc.XPlane(x=-2)
p1y = openmoc.YPlane(y=1)
p2y = openmoc.YPlane(y=-0.5)
p1z = openmoc.ZPlane(z=8)
p2z = openmoc.ZPlane(z=-4)
# Define boundary types
p1x.setBoundaryType(openmoc.VACUUM)
p2x.setBoundaryType(openmoc.REFLECTIVE)
p1y.setBoundaryType(openmoc.PERIODIC)
p2y.setBoundaryType(openmoc.REFLECTIVE)
p1z.setBoundaryType(openmoc.PERIODIC)
p2z.setBoundaryType(openmoc.VACUUM)
# Define halfspaces
h1x = openmoc.Halfspace(-1, p1x)
h2x = openmoc.Halfspace(+1, p2x)
h1y = openmoc.Halfspace(-1, p1y)
h2y = openmoc.Halfspace(+1, p2y)
h1z = openmoc.Halfspace(-1, p1z)
h2z = openmoc.Halfspace(+1, p2z)
# Test getMaxXYZ + MaxXYZboundary
union.addNode(h1x, True)
self.assertEqual(union.getMaxX(), 3)
self.assertEqual(union.getMaxXBoundaryType(), openmoc.VACUUM)
#union.removeHalfspace(p1x, -1) #FIXME seg faults
union = openmoc.Union()
union.addNode(h1y)
self.assertEqual(union.getMaxY(), 1)
self.assertEqual(union.getMaxYBoundaryType(), openmoc.PERIODIC)
#union.removeHalfspace(p1y, -1)
union = openmoc.Union()
union.addNode(h1z)
self.assertEqual(union.getMaxZ(), 8)
self.assertEqual(union.getMaxZBoundaryType(), openmoc.PERIODIC)
#union.removeHalfspace(p1z, -1)
# Test getMinXYZ + MinXYZboundary
union = openmoc.Union()
union.addNode(h2x)
self.assertEqual(union.getMinX(), -2)
self.assertEqual(union.getMinXBoundaryType(), openmoc.REFLECTIVE)
#union.removeHalfspace(h2x)
union = openmoc.Union()
union.addNode(h2y)
self.assertEqual(union.getMinY(), -0.5)
self.assertEqual(union.getMinYBoundaryType(), openmoc.REFLECTIVE)
#union.removeHalfspace(h2y)
union = openmoc.Union()
union.addNode(h2z)
self.assertEqual(union.getMinZ(), -4)
self.assertEqual(union.getMinZBoundaryType(), openmoc.VACUUM)
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)
###############################################################################
log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
log.py_printf('NORMAL', 'Creating surfaces...')
xmin = openmoc.XPlane(x=-5.0, name='xmin')
xmax = openmoc.XPlane(x= 5.0, name='xmax')
ymin = openmoc.YPlane(y=-5.0, name='ymin')
ymax = openmoc.YPlane(y= 5.0, name='ymax')
zmin = openmoc.ZPlane(z=-5.0, name='zmin')
zmax = openmoc.ZPlane(z= 5.0, name='zmax')
xmin.setBoundaryType(openmoc.VACUUM)
xmax.setBoundaryType(openmoc.VACUUM)
ymin.setBoundaryType(openmoc.VACUUM)
ymax.setBoundaryType(openmoc.VACUUM)
zmin.setBoundaryType(openmoc.VACUUM)
zmax.setBoundaryType(openmoc.VACUUM)
###############################################################################
# Creating Cells
###############################################################################
# Creating Materials
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../../')
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-32.13, name='left')
right = openmoc.XPlane(x=32.13, name='right')
top = openmoc.YPlane(y=32.13, name='top')
bottom = openmoc.YPlane(y=-32.13, name='bottom')
left.setBoundaryType(openmoc.REFLECTIVE)
right.setBoundaryType(openmoc.VACUUM)
top.setBoundaryType(openmoc.REFLECTIVE)
bottom.setBoundaryType(openmoc.VACUUM)
boundaries = [left, right, top, bottom]
# Create ZCylinders for the fuel as well as to discretize the moderator into
# rings
fuel_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.54)
moderator_inner_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.58)
moderator_outer_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.62)
###############################################################################
# Creating Cells and Universes
# Creating Materials
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('LRA-mgxs.h5', '')
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-82.5)
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'])
def get_openmoc_surface(openmc_surface):
"""Return an OpenMOC surface corresponding to an OpenMC surface.
Parameters
----------
openmc_surface : openmc.Surface
OpenMC surface
Returns
-------
openmoc_surface : openmoc.Surface
Equivalent OpenMOC surface
"""
cv.check_type('openmc_surface', openmc_surface, openmc.Surface)
surface_id = openmc_surface.id
# If this Material was already created, use it
if surface_id in OPENMOC_SURFACES:
return OPENMOC_SURFACES[surface_id]
# Create an OpenMOC Surface to represent this OpenMC Surface
name = openmc_surface.name
# Determine the type of boundary conditions applied to the Surface
if openmc_surface.boundary_type == 'vacuum':
boundary = openmoc.VACUUM
elif openmc_surface.boundary_type == 'reflective':
boundary = openmoc.REFLECTIVE
elif openmc_surface.boundary_type == 'periodic':
boundary = openmoc.PERIODIC
else:
boundary = openmoc.BOUNDARY_NONE
if openmc_surface.type == 'plane':
A = openmc_surface.a
B = openmc_surface.b
C = openmc_surface.c
D = openmc_surface.d
# OpenMOC uses the opposite sign on D
openmoc_surface = openmoc.Plane(A, B, C, -D, surface_id, name)
elif openmc_surface.type == 'x-plane':
x0 = openmc_surface.x0
openmoc_surface = openmoc.XPlane(x0, surface_id, name)
elif openmc_surface.type == 'y-plane':
y0 = openmc_surface.y0
openmoc_surface = openmoc.YPlane(y0, surface_id, name)
elif openmc_surface.type == 'z-plane':
z0 = openmc_surface.z0
openmoc_surface = openmoc.ZPlane(z0, surface_id, name)
elif openmc_surface.type == 'z-cylinder':
x0 = openmc_surface.x0
y0 = openmc_surface.y0
R = openmc_surface.r
openmoc_surface = openmoc.ZCylinder(x0, y0, R, surface_id, name)
else:
msg = 'Unable to create an OpenMOC Surface from an OpenMC ' \
'Surface of type "{}" since it is not a compatible ' \
'Surface type in OpenMOC'.format(type(openmc_surface))
raise ValueError(msg)
# Set the boundary condition for this Surface
openmoc_surface.setBoundaryType(boundary)
# Add the OpenMC Surface to the global collection of all OpenMC Surfaces
OPENMC_SURFACES[surface_id] = openmc_surface
# Add the OpenMOC Surface to the global collection of all OpenMOC Surfaces
OPENMOC_SURFACES[surface_id] = openmoc_surface
return openmoc_surface
# Creating Materials
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-2.0, name='left')
right = openmoc.XPlane(x=2.0, name='right')
top = openmoc.YPlane(y=-2.0, name='top')
bottom = openmoc.YPlane(y=2.0, name='bottom')
boundaries = [left, right, top, bottom]
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)
###############################################################################
# Creating Cells
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-34.0, name='left')
right = openmoc.XPlane(x=34.0, name='right')
top = openmoc.YPlane(y=-34.0, name='top')
bottom = openmoc.YPlane(y=34.0, name='bottom')
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...')
import openmoc
###############################################################################
# Create dictionary of common surfaces
###############################################################################
surfaces = {}
# Instantiate surfaces
surfaces['Root x-min'] = openmoc.XPlane(x=-12.5, name='Root x-min')
surfaces['Root y-min'] = openmoc.YPlane(y=-12.5, name='Root y-min')
surfaces['Root z-min'] = openmoc.ZPlane(z=-12.5, name='Root z-min')
surfaces['Root x-max'] = openmoc.XPlane(x=12.5, name='Root x-max')
surfaces['Root y-max'] = openmoc.YPlane(y=12.5, name='Root y-max')
surfaces['Root z-max'] = openmoc.ZPlane(z=12.5, name='Root z-max')
surfaces['Root x-min'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Root y-min'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Root z-min'].setBoundaryType(openmoc.REFLECTIVE)
surfaces['Root x-max'].setBoundaryType(openmoc.VACUUM)
surfaces['Root y-max'].setBoundaryType(openmoc.VACUUM)
surfaces['Root z-max'].setBoundaryType(openmoc.VACUUM)
########################### Creating Materials ############################
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../../')
###############################################################################
########################### Creating Surfaces #############################
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
xmin = openmoc.XPlane(x=-32.13, name='xmin')
xmax = openmoc.XPlane(x=32.13, name='xmax')
ymin = openmoc.YPlane(y=-32.13, name='ymin')
ymax = openmoc.YPlane(y=32.13, name='ymax')
zmin = openmoc.ZPlane(z=-32.13, name='zmin')
zmax = openmoc.ZPlane(z=32.13, name='zmax')
xmin.setBoundaryType(openmoc.REFLECTIVE)
xmax.setBoundaryType(openmoc.VACUUM)
ymin.setBoundaryType(openmoc.VACUUM)
ymax.setBoundaryType(openmoc.REFLECTIVE)
# Create ZCylinders for the fuel as well as to discretize the moderator into
# rings
fuel_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.54)
moderator_inner_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.58)
moderator_outer_radius = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.62)
def _run_openmoc(self):
"""Instantiate a complex region Geometry."""
# ----------------
# / \
# --------------- c2 (p22,p23) - u2 - c2a (p11)
# / /
# u_r <- c_r (p1,p2) - u1 - c1 (p11,p12,p13)
# \ \
# ------------- c3
root_universe = openmoc.Universe(name='root universe')
root_cell = openmoc.Cell(name='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)
openmoc.set_log_level('NORMAL')
for cell in [root_cell, c1, c2, c2a, c3]:
py_printf('NORMAL', 'Cell: %s', cell.getName())
py_printf('NORMAL', 'MinX: %f', cell.getMinX())
py_printf('NORMAL', 'MinXBoundaryType: %s',
cell.getMinXBoundaryType())
py_printf('NORMAL', 'MinY: %f', cell.getMinY())
py_printf('NORMAL', 'MinYBoundaryType: %s',
cell.getMinYBoundaryType())
py_printf('NORMAL', 'MinZ: %f', cell.getMinZ())
py_printf('NORMAL', 'MinZBoundaryType: %s',
cell.getMinZBoundaryType())
py_printf('NORMAL', 'MaxX: %f', cell.getMaxX())
py_printf('NORMAL', 'MaxXBoundaryType: %s',
cell.getMaxXBoundaryType())
py_printf('NORMAL', 'MaxY: %f', cell.getMaxY())
py_printf('NORMAL', 'MaxYBoundaryType: %s',
cell.getMaxYBoundaryType())
py_printf('NORMAL', 'MaxZ: %f', cell.getMaxZ())
py_printf('NORMAL', 'MaxZBoundaryType: %s',
cell.getMaxZBoundaryType())
py_printf('NORMAL', '')
# Creating Materials
###############################################################################
openmoc.log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-5.0, name='left')
right = openmoc.XPlane(x=5.0, name='right')
bottom = openmoc.YPlane(y=-5.0, name='bottom')
top = openmoc.YPlane(y=5.0, name='top')
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'])
def get_openmoc_surface(opencg_surface):
if not isinstance(opencg_surface, opencg.Surface):
msg = 'Unable to create an OpenMoC Surface from {0} which ' \
'is not an OpenCG Surface'.format(opencg_surface)
raise ValueError(msg)
global OPENMOC_SURFACES
surface_id = opencg_surface._id
# If this Surface was already created, use it
if surface_id in OPENMOC_SURFACES:
return OPENMOC_SURFACES[surface_id]
# Create an OpenMOC Surface to represent this OpenCG Surface
name = opencg_surface._name
# Correct for OpenMOC's syntax for Surfaces dividing Cells
boundary = opencg_surface._boundary_type
if boundary == 'vacuum':
boundary = openmoc.VACUUM
elif boundary == 'reflective':
boundary = openmoc.REFLECTIVE
elif boundary == 'interface':
boundary = openmoc.BOUNDARY_NONE
if opencg_surface._type == 'plane':
A = opencg_surface._coeffs['A']
B = opencg_surface._coeffs['B']
D = opencg_surface._coeffs['D']
openmoc_surface = openmoc.Plane(A, B, D, surface_id, name)
elif opencg_surface._type == 'x-plane':
x0 = opencg_surface._coeffs['x0']
openmoc_surface = openmoc.XPlane(x0, int(surface_id), name)
elif opencg_surface._type == 'y-plane':
y0 = opencg_surface._coeffs['y0']
openmoc_surface = openmoc.YPlane(y0, surface_id, name)
elif opencg_surface._type == 'z-plane':
z0 = opencg_surface._coeffs['z0']
openmoc_surface = openmoc.ZPlane(z0, surface_id, name)
elif opencg_surface._type == 'z-cylinder':
x0 = opencg_surface._coeffs['x0']
y0 = opencg_surface._coeffs['y0']
R = opencg_surface._coeffs['R']
openmoc_surface = openmoc.ZCylinder(x0, y0, R, surface_id, name)
else:
msg = 'Unable to create an OpenMOC Surface from an OpenCG ' \
'Surface of type {0} since it is not a compatible ' \
'Surface type in OpenMOC'.format(opencg_surface._type)
raise ValueError(msg)
# Set the boundary condition for this Surface
openmoc_surface.setBoundaryType(boundary)
# Add the OpenMOC Surface to the global collection of all OpenMOC Surfaces
OPENMOC_SURFACES[surface_id] = openmoc_surface
# Add the OpenCG Surface to the global collection of all OpenCG Surfaces
OPENCG_SURFACES[surface_id] = opencg_surface
# FIXME
openmoc_surface.thisown = 0
return openmoc_surface
moderator.setSigmaT(numpy.array([0.841545641]))
moderator.setSigmaF(numpy.array([0.0]))
moderator.setNuSigmaF(numpy.array([0.0]))
moderator.setSigmaS(numpy.array([0.837794542]))
moderator.setChi(numpy.array([1.0]))
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
zcylinder = openmoc.ZCylinder(x=0.0, y=0.0, radius=0.4)
left = openmoc.XPlane(x=-0.635)
right = openmoc.XPlane(x=0.635)
top = openmoc.YPlane(y=0.635)
bottom = openmoc.YPlane(y=-0.635)
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_cell = openmoc.Cell(name='fuel')
fuel_cell.setFill(fuel)
# Creating Materials
###############################################################################
log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
log.py_printf('NORMAL', 'Creating surfaces...')
xmin = openmoc.XPlane(x=-20.0, name='xmin')
xmax = openmoc.XPlane(x=20.0, name='xmax')
ymin = openmoc.YPlane(y=-20.0, name='ymin')
ymax = openmoc.YPlane(y=20.0, name='ymax')
zmin = openmoc.ZPlane(z=-20.0, name='zmin')
zmax = openmoc.ZPlane(z=20.0, name='zmax')
xmin.setBoundaryType(openmoc.VACUUM)
xmax.setBoundaryType(openmoc.VACUUM)
ymin.setBoundaryType(openmoc.VACUUM)
ymax.setBoundaryType(openmoc.VACUUM)
zmin.setBoundaryType(openmoc.VACUUM)
zmax.setBoundaryType(openmoc.VACUUM)
###############################################################################
# Creating Cells
###############################################################################
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 get_openmoc_surface(opencg_surface):
"""Return an OpenMOC surface corresponding to an OpenCG surface.
Parameters
----------
opencg_surface : opencg.Surface
OpenCG surface
Returns
-------
openmoc_surface : openmoc.Surface
Equivalent OpenMOC surface
"""
cv.check_type('opencg_surface', opencg_surface, opencg.Surface)
global OPENMOC_SURFACES
surface_id = opencg_surface.id
# If this Surface was already created, use it
if surface_id in OPENMOC_SURFACES:
return OPENMOC_SURFACES[surface_id]
# Create an OpenMOC Surface to represent this OpenCG Surface
name = str(opencg_surface.name)
# Correct for OpenMOC's syntax for Surfaces dividing Cells
boundary = opencg_surface.boundary_type
if boundary == 'vacuum':
boundary = openmoc.VACUUM
elif boundary == 'reflective':
boundary = openmoc.REFLECTIVE
elif boundary == 'interface':
boundary = openmoc.BOUNDARY_NONE
if opencg_surface.type == 'plane':
A = opencg_surface.a
B = opencg_surface.b
C = opencg_surface.c
D = opencg_surface.d
openmoc_surface = openmoc.Plane(A, B, C, D, surface_id, name)
elif opencg_surface.type == 'x-plane':
x0 = opencg_surface.x0
openmoc_surface = openmoc.XPlane(x0, int(surface_id), name)
elif opencg_surface.type == 'y-plane':
y0 = opencg_surface.y0
openmoc_surface = openmoc.YPlane(y0, surface_id, name)
elif opencg_surface.type == 'z-plane':
z0 = opencg_surface.z0
openmoc_surface = openmoc.ZPlane(z0, surface_id, name)
elif opencg_surface.type == 'z-cylinder':
x0 = opencg_surface.x0
y0 = opencg_surface.y0
R = opencg_surface.r
openmoc_surface = openmoc.ZCylinder(x0, y0, R, surface_id, name)
else:
msg = 'Unable to create an OpenMOC Surface from an OpenCG ' \
'Surface of type {0} since it is not a compatible ' \
'Surface type in OpenMOC'.format(opencg_surface.type)
raise ValueError(msg)
# Set the boundary condition for this Surface
openmoc_surface.setBoundaryType(boundary)
# Add the OpenMOC Surface to the global collection of all OpenMOC Surfaces
OPENMOC_SURFACES[surface_id] = openmoc_surface
# Add the OpenCG Surface to the global collection of all OpenCG Surfaces
OPENCG_SURFACES[surface_id] = opencg_surface
return openmoc_surface
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()
infinite_medium.setNumEnergyGroups(2)
infinite_medium.setSigmaF(sigma_f)
infinite_medium.setNuSigmaF(nu_sigma_f)
infinite_medium.setSigmaS(sigma_s.flat)
infinite_medium.setChi(chi)
infinite_medium.setSigmaT(sigma_t)
###############################################################################
# Creating Surfaces
###############################################################################
openmoc.log.py_printf('NORMAL', 'Creating surfaces...')
left = openmoc.XPlane(x=-100.0, name='left')
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)
###############################################################################
log.py_printf('NORMAL', 'Importing materials data from HDF5...')
materials = openmoc.materialize.load_from_hdf5('c5g7-mgxs.h5', '../')
###############################################################################
# Creating Surfaces
###############################################################################
log.py_printf('NORMAL', 'Creating surfaces...')
xmin = openmoc.XPlane(x=-34.0, name='xmin')
xmax = openmoc.XPlane(x= 34.0, name='xmax')
ymin = openmoc.YPlane(y=-34.0, name='ymin')
ymax = openmoc.YPlane(y= 34.0, name='ymax')
zmin = openmoc.ZPlane(z=-0.5, name='zmin')
zmax = openmoc.ZPlane(z= 0.5, name='zmax')
xmin.setBoundaryType(openmoc.REFLECTIVE)
xmax.setBoundaryType(openmoc.REFLECTIVE)
ymin.setBoundaryType(openmoc.REFLECTIVE)
ymax.setBoundaryType(openmoc.REFLECTIVE)
zmin.setBoundaryType(openmoc.REFLECTIVE)
zmax.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))
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 _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")
