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Improvements to tests

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This commit is contained in:
Patrick Shriwise 2023-03-27 16:15:38 -05:00
parent 13a9e8fae4
commit ab403b2fc8
2 changed files with 26 additions and 21 deletions
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22
tests/unit_tests/test_cylindrical_mesh.py
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@ -149,12 +149,12 @@ def _check_void_cylindrical_tally(statepoint_filename):
with openmc.StatePoint(statepoint_filename) as sp:
flux_tally = sp.tallies[1]
mesh = flux_tally.find_filter(openmc.MeshFilter).mesh
neutron_flux = flux_tally.get_reshaped_data().squeeze() / mesh.volumes.flatten()
flux_diff = np.diff(neutron_flux)
# ensure flux values are monotonically decreasing due to
# geometric attenuation
assert (flux_diff < 0.0).all()
neutron_flux = flux_tally.get_reshaped_data().squeeze()
# we expect the tally results to be the same as the mesh grid width
# for these cases
print(neutron_flux)
d_r = mesh.r_grid[1] - mesh.r_grid[0]
assert neutron_flux == pytest.approx(d_r)
def test_void_geom_pnt_src(run_in_tmpdir, void_coincident_geom_model):
src = openmc.Source()
@ -168,11 +168,15 @@ def test_void_geom_pnt_src(run_in_tmpdir, void_coincident_geom_model):
def test_void_geom_boundary_src(run_in_tmpdir, void_coincident_geom_model):
# update source to a number of points on the outside of the cylinder
# with directions pointing toward the origin
bbox = void_coincident_geom_model.geometry.bounding_box
outer_r = bbox[1][0] - 0.0001
# can't source particle directly on the geometry boundary
outer_r = bbox[1][0] - 1e-08
radial_vals = np.linspace(0.0, 2.0*np.pi, 100)
n_sources = 100
radial_vals = np.linspace(0.0, 2.0*np.pi, n_sources)
sources = []
@ -185,7 +189,7 @@ def test_void_geom_boundary_src(run_in_tmpdir, void_coincident_geom_model):
u = -pnt
src.space = openmc.stats.Point(outer_r*pnt)
src.angle = openmc.stats.Monodirectional(u)
src.strength = 0.5/n_sources
sources.append(src)
void_coincident_geom_model.settings.source = sources

25
tests/unit_tests/test_spherical_mesh.py
View file

@ -155,11 +155,11 @@ def _check_void_spherical_tally(statepoint_filename):
with openmc.StatePoint(statepoint_filename) as sp:
flux_tally = sp.tallies[1]
mesh = flux_tally.find_filter(openmc.MeshFilter).mesh
neutron_flux = flux_tally.get_reshaped_data().squeeze() / mesh.volumes.flatten()
flux_diff = np.diff(neutron_flux)
# ensure flux values are monotonically decreasing due to
# geometric attenuation
assert (flux_diff < 0.0).all()
neutron_flux = flux_tally.get_reshaped_data().squeeze()
# the flux values for each bin should equal the width
# width of the mesh bins
d_r = mesh.r_grid[1] - mesh.r_grid[0]
assert neutron_flux == pytest.approx(d_r)
def test_void_geom_pnt_src(run_in_tmpdir, void_coincident_geom_model):
@ -169,22 +169,21 @@ def test_void_geom_pnt_src(run_in_tmpdir, void_coincident_geom_model):
src.energy = openmc.stats.Discrete([14.06e6], [1])
void_coincident_geom_model.settings.source = src
# run model and check tally results
sp_filename = void_coincident_geom_model.run()
_check_void_spherical_tally(sp_filename)
def test_void_geom_boundary_src(run_in_tmpdir, void_coincident_geom_model):
# update source to a number of points on the outside of the sphere
# with directions pointing toward the origin
# sources
phi_vals = np.linspace(0, np.pi, 20)
theta_vals = np.linspace(0, 2.0*np.pi, 20)
n_sources = 20
phi_vals = np.linspace(0, np.pi, n_sources)
theta_vals = np.linspace(0, 2.0*np.pi, n_sources)
bbox = void_coincident_geom_model.geometry.bounding_box
# can't source particles directly on the geometry boundary
outer_r = bbox[1][0] - 0.00001
outer_r = bbox[1][0] - 1e-08
sources = []
@ -199,11 +198,13 @@ def test_void_geom_boundary_src(run_in_tmpdir, void_coincident_geom_model):
u = -pnt
src.space = openmc.stats.Point(outer_r*pnt)
src.angle = openmc.stats.Monodirectional(u)
# set source strengths so that we can still expect
# a tally value of 0.5
src.strength = 0.5/n_sources
sources.append(src)
void_coincident_geom_model.settings.source = sources
sp_filename = void_coincident_geom_model.run()
_check_void_spherical_tally(sp_filename)