mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-26 21:25:36 -04:00
72 lines
2.6 KiB
Python
72 lines
2.6 KiB
Python
import openmc
|
|
import pytest
|
|
|
|
from tests.testing_harness import PyAPITestHarness
|
|
|
|
|
|
@pytest.fixture
|
|
def model():
|
|
model = openmc.model.Model()
|
|
mat = openmc.Material()
|
|
mat.set_density('g/cm3', 2.6989)
|
|
mat.add_nuclide('Al27', 1.0)
|
|
model.materials.append(mat)
|
|
|
|
cyl = openmc.XCylinder(r=1.0, boundary_type='vacuum')
|
|
x_plane_left = openmc.XPlane(-1.0, boundary_type='vacuum')
|
|
x_plane_center = openmc.XPlane(1.0)
|
|
x_plane_right = openmc.XPlane(1.0e9, boundary_type='vacuum')
|
|
|
|
inner_cyl_left = openmc.Cell()
|
|
inner_cyl_right = openmc.Cell()
|
|
outer_cyl = openmc.Cell()
|
|
|
|
inner_cyl_left.region = -cyl & +x_plane_left & -x_plane_center
|
|
inner_cyl_right.region = -cyl & +x_plane_center & -x_plane_right
|
|
outer_cyl.region = ~(-cyl & +x_plane_left & -x_plane_right)
|
|
inner_cyl_right.fill = mat
|
|
model.geometry = openmc.Geometry([inner_cyl_left, inner_cyl_right, outer_cyl])
|
|
|
|
source = openmc.IndependentSource()
|
|
source.space = openmc.stats.Point((0, 0, 0))
|
|
source.angle = openmc.stats.Monodirectional()
|
|
source.energy = openmc.stats.Discrete([14.0e6], [1.0])
|
|
source.particle = 'neutron'
|
|
|
|
model.settings.particles = 10000
|
|
model.settings.run_mode = 'fixed source'
|
|
model.settings.batches = 1
|
|
model.settings.photon_transport = True
|
|
model.settings.electron_treatment = 'ttb'
|
|
model.settings.cutoff = {'energy_photon' : 1000.0}
|
|
model.settings.source = source
|
|
|
|
surface_filter = openmc.SurfaceFilter(cyl)
|
|
particle_filter = openmc.ParticleFilter(['neutron', 'photon', 'electron', 'positron'])
|
|
current_tally = openmc.Tally()
|
|
current_tally.filters = [surface_filter, particle_filter]
|
|
current_tally.scores = ['current']
|
|
tally_tracklength = openmc.Tally()
|
|
tally_tracklength.filters = [particle_filter]
|
|
tally_tracklength.scores = ['total', '(n,gamma)'] # heating doesn't work with tracklength
|
|
tally_tracklength.nuclides = ['Al27', 'total']
|
|
tally_tracklength.estimator = 'tracklength'
|
|
tally_collision = openmc.Tally()
|
|
tally_collision.filters = [particle_filter]
|
|
tally_collision.scores = ['total', 'heating', '(n,gamma)']
|
|
tally_collision.nuclides = ['Al27', 'total']
|
|
tally_collision.estimator = 'collision'
|
|
tally_analog = openmc.Tally()
|
|
tally_analog.filters = [particle_filter]
|
|
tally_analog.scores = ['total', 'heating', '(n,gamma)']
|
|
tally_analog.nuclides = ['Al27', 'total']
|
|
tally_analog.estimator = 'analog'
|
|
model.tallies.extend([current_tally, tally_tracklength,
|
|
tally_collision, tally_analog])
|
|
|
|
return model
|
|
|
|
|
|
def test_photon_production(model):
|
|
harness = PyAPITestHarness('statepoint.1.h5', model)
|
|
harness.main()
|