def test_mg_max_order():
create_library()
model = slab_mg()
model.settings.max_order = 1
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
def test_mg_survival_biasing():
create_library()
model = slab_mg()
model.settings.survival_biasing = True
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
def test_mg_basic_delayed():
create_library()
model = slab_mg(num_regions=6,
mat_names=[
'vec beta', 'vec no beta', 'matrix beta',
'matrix no beta', 'vec group beta', 'matrix group beta'
])
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
def test_mg_basic():
create_library()
mat_names = [
'base leg', 'base tab', 'base hist', 'base matrix', 'base ang', 'micro'
]
model = slab_mg(num_regions=6, mat_names=mat_names)
# Modify the last material to be a microscopic combination of nuclides
model.materials[-1] = openmc.Material(name='micro', material_id=6)
model.materials[-1].set_density("sum")
model.materials[-1].add_nuclide("mat_1", 0.5)
model.materials[-1].add_nuclide("mat_6", 0.5)
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from openmc.examples import slab_mg
if __name__ == '__main__':
model = slab_mg()
model.settings.survival_biasing = True
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from openmc.examples import slab_mg
if __name__ == '__main__':
model = slab_mg()
model.settings.survival_biasing = True
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import HashedPyAPITestHarness
import openmc
from openmc.examples import slab_mg
if __name__ == '__main__':
model = slab_mg(as_macro=False)
# Instantiate a tally mesh
mesh = openmc.Mesh(mesh_id=1)
mesh.type = 'regular'
mesh.dimension = [1, 1, 10]
mesh.lower_left = [0.0, 0.0, 0.0]
mesh.upper_right = [10, 10, 5]
# Instantiate some tally filters
energy_filter = openmc.EnergyFilter([0.0, 20.0e6])
energyout_filter = openmc.EnergyoutFilter([0.0, 20.0e6])
energies = [1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6]
matching_energy_filter = openmc.EnergyFilter(energies)
matching_eout_filter = openmc.EnergyoutFilter(energies)
mesh_filter = openmc.MeshFilter(mesh)
mat_filter = openmc.MaterialFilter(model.materials)
nuclides = model.xs_data
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from openmc.examples import slab_mg
if __name__ == '__main__':
model = slab_mg(reps=['iso'])
model.settings.tabular_legendre = {'enable': False}
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from openmc.examples import slab_mg
if __name__ == '__main__':
model = slab_mg(reps=['iso'])
model.settings.max_order = 1
harness = PyAPITestHarness('statepoint.10.h5', model)
harness.main()
def test_mg_tallies():
create_library()
model = slab_mg()
# Instantiate a tally mesh
mesh = openmc.RegularMesh(mesh_id=1)
mesh.dimension = [10, 1, 1]
mesh.lower_left = [0.0, 0.0, 0.0]
mesh.upper_right = [929.45, 1000, 1000]
# Instantiate some tally filters
energy_filter = openmc.EnergyFilter([0.0, 20.0e6])
energyout_filter = openmc.EnergyoutFilter([0.0, 20.0e6])
energies = [0.0, 0.625, 20.0e6]
matching_energy_filter = openmc.EnergyFilter(energies)
matching_eout_filter = openmc.EnergyoutFilter(energies)
mesh_filter = openmc.MeshFilter(mesh)
mat_filter = openmc.MaterialFilter(model.materials)
nuclides = model.xs_data
scores_with_nuclides = [
'total', 'absorption', 'fission', 'nu-fission', 'inverse-velocity',
'prompt-nu-fission', 'delayed-nu-fission', 'kappa-fission', 'events',
'decay-rate'
]
scores_without_nuclides = scores_with_nuclides + ['flux']
for do_nuclides, scores in ((False, scores_without_nuclides),
(True, scores_with_nuclides)):
t = openmc.Tally()
t.filters = [mesh_filter]
t.estimator = 'analog'
t.scores = scores
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
t = openmc.Tally()
t.filters = [mesh_filter]
t.estimator = 'tracklength'
t.scores = scores
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
# Impose energy bins that dont match the MG structure and those
# that do
for match_energy_bins in [False, True]:
if match_energy_bins:
e_filter = matching_energy_filter
eout_filter = matching_eout_filter
else:
e_filter = energy_filter
eout_filter = energyout_filter
t = openmc.Tally()
t.filters = [mat_filter, e_filter]
t.estimator = 'analog'
t.scores = scores + ['scatter', 'nu-scatter']
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
t = openmc.Tally()
t.filters = [mat_filter, e_filter]
t.estimator = 'collision'
t.scores = scores
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
t = openmc.Tally()
t.filters = [mat_filter, e_filter]
t.estimator = 'tracklength'
t.scores = scores
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
t = openmc.Tally()
t.filters = [mat_filter, e_filter, eout_filter]
t.scores = ['scatter', 'nu-scatter', 'nu-fission']
if do_nuclides:
t.nuclides = nuclides
model.tallies.append(t)
harness = MGXSTestHarness('statepoint.10.h5', model)
harness.main()