mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-26 21:25:36 -04:00
ecb0a3361f
Co-authored-by: Gavin Ridley <gavin.keith.ridley@gmail.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
97 lines
3.5 KiB
Python
97 lines
3.5 KiB
Python
import numpy as np
|
|
|
|
import openmc
|
|
import openmc.lib
|
|
|
|
import pytest
|
|
from tests.testing_harness import PyAPITestHarness
|
|
|
|
pytestmark = pytest.mark.skipif(
|
|
not openmc.lib._dagmc_enabled(),
|
|
reason="DAGMC CAD geometry is not enabled.")
|
|
|
|
|
|
@pytest.fixture
|
|
def pin_lattice_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 = openmc.Model()
|
|
model.materials = openmc.Materials([fuel, cladding, water])
|
|
|
|
### GEOMETRY ###
|
|
# create the DAGMC universe
|
|
pincell_univ = openmc.DAGMCUniverse(filename='dagmc.h5m', auto_geom_ids=True)
|
|
|
|
# creates another DAGMC universe, this time with within a bounded cell
|
|
bound_pincell_universe = openmc.DAGMCUniverse(filename='dagmc.h5m').bounded_universe()
|
|
# uses the bound_dag_cell as the root argument to test the type checks in openmc.Geometry
|
|
bound_pincell_geometry = openmc.Geometry(root=bound_pincell_universe)
|
|
# assigns the bound_dag_geometry to the model to test the type checks in model.Geometry setter
|
|
model.geometry = bound_pincell_geometry
|
|
|
|
# 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])
|
|
|
|
# add a cell instance tally
|
|
tally = openmc.Tally(name='cell instance tally')
|
|
# using scattering
|
|
cell_instance_filter = openmc.CellInstanceFilter(((4, 0), (4, 1), (4, 2), (4, 3), (4, 4)))
|
|
tally.filters = [cell_instance_filter]
|
|
tally.scores = ['scatter']
|
|
model.tallies = [tally]
|
|
|
|
# settings
|
|
model.settings.particles = 100
|
|
model.settings.batches = 10
|
|
model.settings.inactive = 5
|
|
model.settings.output = {'summary' : False}
|
|
model.settings.source = openmc.IndependentSource(
|
|
space=openmc.stats.Box((-10., -10., -24.), (10., 10., 24.)),
|
|
constraints={'fissionable': True},
|
|
)
|
|
|
|
return model
|
|
|
|
|
|
def test_univ(pin_lattice_model):
|
|
harness = PyAPITestHarness('statepoint.10.h5', model=pin_lattice_model)
|
|
harness.main()
|