def _build_inputs(self):
model = openmc.model.Model()
# settings
model.settings.batches = 5
model.settings.inactive = 0
model.settings.particles = 100
source = openmc.Source(space=Box([-4, -4, -4], [4, 4, 4]))
model.settings.source = source
model.settings.dagmc = True
model.settings.export_to_xml()
# geometry
dag_univ = openmc.DAGMCUniverse("dagmc.h5m", auto_geom_ids=True)
model.geometry = openmc.Geometry(dag_univ)
# tally
tally = openmc.Tally()
tally.scores = ['total']
tally.filters = [openmc.CellFilter(2)]
model.tallies = [tally]
model.tallies.export_to_xml()
model.export_to_xml()
def dagmc_model(request):
model = openmc.model.Model()
# settings
model.settings.batches = 5
model.settings.inactive = 0
model.settings.particles = 100
model.settings.temperature = {'tolerance': 50.0}
model.settings.verbosity = 1
source_box = openmc.stats.Box([-4, -4, -4], [4, 4, 4])
source = openmc.Source(space=source_box)
model.settings.source = source
# geometry
dagmc_universe = openmc.DAGMCUniverse('dagmc.h5m')
model.geometry = openmc.Geometry(dagmc_universe)
# tally
tally = openmc.Tally()
tally.scores = ['total']
tally.filters = [openmc.CellFilter(1)]
model.tallies = [tally]
# materials
u235 = openmc.Material(name="no-void fuel")
u235.add_nuclide('U235', 1.0, 'ao')
u235.set_density('g/cc', 11)
u235.id = 40
u235.temperature = 320
water = openmc.Material(name="water")
water.add_nuclide('H1', 2.0, 'ao')
water.add_nuclide('O16', 1.0, 'ao')
water.set_density('g/cc', 1.0)
water.add_s_alpha_beta('c_H_in_H2O')
water.id = 41
mats = openmc.Materials([u235, water])
model.materials = mats
# location of dagmc file in test directory
dagmc_file = request.fspath.dirpath() + "/dagmc.h5m"
# move to a temporary directory
with cdtemp():
shutil.copyfile(dagmc_file, "./dagmc.h5m")
model.export_to_xml()
openmc.lib.init()
yield
openmc.lib.finalize()
def model():
model = openmc.model.Model()
# settings
model.settings.batches = 5
model.settings.inactive = 0
model.settings.particles = 100
source_box = openmc.stats.Box([-4, -4, -4], [4, 4, 4])
source = openmc.Source(space=source_box)
model.settings.source = source
model.settings.dagmc = True
# geometry
dag_univ = openmc.DAGMCUniverse("dagmc.h5m")
model.geometry = openmc.Geometry(dag_univ)
# tally
tally = openmc.Tally()
tally.scores = ['total']
tally.filters = [openmc.CellFilter(1)]
model.tallies = [tally]
# materials
u235 = openmc.Material(name="no-void fuel")
u235.add_nuclide('U235', 1.0, 'ao')
u235.set_density('g/cc', 11)
u235.id = 40
water = openmc.Material(name="water")
water.add_nuclide('H1', 2.0, 'ao')
water.add_nuclide('O16', 1.0, 'ao')
water.set_density('g/cc', 1.0)
water.add_s_alpha_beta('c_H_in_H2O')
water.id = 41
mats = openmc.Materials([u235, water])
model.materials = mats
return model
def _build_inputs(self):
model = openmc.model.Model()
### MATERIALS ###
fuel = openmc.Material(name='no-void fuel')
fuel.set_density('g/cc', 10.29769)
fuel.add_nuclide('U234', 0.93120485)
fuel.add_nuclide('U235', 0.00055815)
fuel.add_nuclide('U238', 0.022408)
fuel.add_nuclide('O16', 0.045829)
cladding = openmc.Material(name='clad')
cladding.set_density('g/cc', 6.55)
cladding.add_nuclide('Zr90', 0.021827)
cladding.add_nuclide('Zr91', 0.00476)
cladding.add_nuclide('Zr92', 0.0072758)
cladding.add_nuclide('Zr94', 0.0073734)
cladding.add_nuclide('Zr96', 0.0011879)
water = openmc.Material(name='water')
water.set_density('g/cc', 0.740582)
water.add_nuclide('H1', 0.049457)
water.add_nuclide('O16', 0.024672)
water.add_nuclide('B10', 8.0042e-06)
water.add_nuclide('B11', 3.2218e-05)
water.add_s_alpha_beta('c_H_in_H2O')
model.materials = openmc.Materials([fuel, cladding, water])
### GEOMETRY ###
# create the DAGMC universe
pincell_univ = openmc.DAGMCUniverse(filename='dagmc.h5m',
auto_geom_ids=True)
# create a 2 x 2 lattice using the DAGMC pincell
pitch = np.asarray((24.0, 24.0))
lattice = openmc.RectLattice()
lattice.pitch = pitch
lattice.universes = [[pincell_univ] * 2] * 2
lattice.lower_left = -pitch
left = openmc.XPlane(x0=-pitch[0],
name='left',
boundary_type='reflective')
right = openmc.XPlane(x0=pitch[0],
name='right',
boundary_type='reflective')
front = openmc.YPlane(y0=-pitch[1],
name='front',
boundary_type='reflective')
back = openmc.YPlane(y0=pitch[1],
name='back',
boundary_type='reflective')
# clip the DAGMC geometry at +/- 10 cm w/ CSG planes
bottom = openmc.ZPlane(z0=-10.0,
name='bottom',
boundary_type='reflective')
top = openmc.ZPlane(z0=10.0, name='top', boundary_type='reflective')
bounding_region = +left & -right & +front & -back & +bottom & -top
bounding_cell = openmc.Cell(fill=lattice, region=bounding_region)
model.geometry = openmc.Geometry([bounding_cell])
# settings
model.settings.particles = 100
model.settings.batches = 10
model.settings.inactive = 2
model.settings.output = {'summary': False}
model.export_to_xml()