OpenMC/tests/unit_tests/conftest.py
Patrick Shriwise eda39ad9ca
Python source class refactor (#2524)
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
2023-06-20 21:27:55 -05:00

124 lines
3.6 KiB
Python

import openmc
import pytest
from tests.regression_tests import config
@pytest.fixture(scope='module')
def mpi_intracomm():
if config['mpi']:
from mpi4py import MPI
return MPI.COMM_WORLD
else:
return None
@pytest.fixture(scope='module')
def uo2():
m = openmc.Material(material_id=100, name='UO2')
m.add_nuclide('U235', 1.0)
m.add_nuclide('O16', 2.0)
m.set_density('g/cm3', 10.0)
m.depletable = True
return m
@pytest.fixture(scope='module')
def water():
m = openmc.Material(name='light water')
m.add_nuclide('H1', 2.0)
m.add_nuclide('O16', 1.0)
m.set_density('g/cm3', 1.0)
m.add_s_alpha_beta('c_H_in_H2O')
return m
@pytest.fixture(scope='module')
def sphere_model():
model = openmc.model.Model()
m = openmc.Material()
m.add_nuclide('U235', 1.0)
m.set_density('g/cm3', 1.0)
model.materials.append(m)
sph = openmc.Sphere(boundary_type='vacuum')
c = openmc.Cell(fill=m, region=-sph)
model.geometry.root_universe = openmc.Universe(cells=[c])
model.settings.particles = 100
model.settings.batches = 10
model.settings.run_mode = 'fixed source'
model.settings.source = openmc.IndependentSource(space=openmc.stats.Point())
return model
@pytest.fixture
def cell_with_lattice():
m_inside = [openmc.Material(), openmc.Material(), None, openmc.Material()]
m_outside = openmc.Material()
cyl = openmc.ZCylinder(r=1.0)
inside_cyl = openmc.Cell(fill=m_inside, region=-cyl)
outside_cyl = openmc.Cell(fill=m_outside, region=+cyl)
univ = openmc.Universe(cells=[inside_cyl, outside_cyl])
lattice = openmc.RectLattice(name='My Lattice')
lattice.lower_left = (-4.0, -4.0)
lattice.pitch = (4.0, 4.0)
lattice.universes = [[univ, univ], [univ, univ]]
main_cell = openmc.Cell(fill=lattice)
return ([inside_cyl, outside_cyl, main_cell],
[m_inside[0], m_inside[1], m_inside[3], m_outside],
univ, lattice)
@pytest.fixture
def mixed_lattice_model(uo2, water):
cyl = openmc.ZCylinder(r=0.4)
c1 = openmc.Cell(fill=uo2, region=-cyl)
c1.temperature = 600.0
c2 = openmc.Cell(fill=water, region=+cyl)
pin = openmc.Universe(cells=[c1, c2])
empty = openmc.Cell()
empty_univ = openmc.Universe(cells=[empty])
hex_lattice = openmc.HexLattice()
hex_lattice.center = (0.0, 0.0)
hex_lattice.pitch = (1.2, 10.0)
outer_ring = [pin]*6
inner_ring = [empty_univ]
axial_level = [outer_ring, inner_ring]
hex_lattice.universes = [axial_level]*3
hex_lattice.outer = empty_univ
cell_hex = openmc.Cell(fill=hex_lattice)
u = openmc.Universe(cells=[cell_hex])
rotated_cell_hex = openmc.Cell(fill=u)
rotated_cell_hex.rotation = (0., 0., 30.)
ur = openmc.Universe(cells=[rotated_cell_hex])
d = 6.0
rect_lattice = openmc.RectLattice()
rect_lattice.lower_left = (-d, -d)
rect_lattice.pitch = (d, d)
rect_lattice.outer = empty_univ
rect_lattice.universes = [
[ur, empty_univ],
[empty_univ, u]
]
xmin = openmc.XPlane(-d, boundary_type='periodic')
xmax = openmc.XPlane(d, boundary_type='periodic')
xmin.periodic_surface = xmax
ymin = openmc.YPlane(-d, boundary_type='periodic')
ymax = openmc.YPlane(d, boundary_type='periodic')
main_cell = openmc.Cell(fill=rect_lattice,
region=+xmin & -xmax & +ymin & -ymax)
# Create geometry and use unique material in each fuel cell
geometry = openmc.Geometry([main_cell])
geometry.determine_paths()
c1.fill = [water.clone() for i in range(c1.num_instances)]
return openmc.model.Model(geometry)