OpenMC/tests/regression_tests/unstructured_mesh/test.py

326 lines
11 KiB
Python

import filecmp
import glob
from itertools import product
import os
import warnings
import openmc
import openmc.lib
import numpy as np
import pytest
from tests.testing_harness import PyAPITestHarness
class UnstructuredMeshTest(PyAPITestHarness):
ELEM_PER_VOXEL = 12
def __init__(self,
statepoint_name,
model,
inputs_true='inputs_true.dat',
holes=False,
scale_factor=10.0):
super().__init__(statepoint_name, model, inputs_true)
self.holes = holes # holes in the test mesh
self.scale_bounding_cell(scale_factor)
def scale_bounding_cell(self, scale_factor):
geometry = self._model.geometry
for surface in geometry.get_all_surfaces().values():
if surface.boundary_type != 'vacuum':
continue
for coeff in surface._coefficients:
surface._coefficients[coeff] *= scale_factor
def _compare_results(self):
with openmc.StatePoint(self._sp_name) as sp:
# check some properties of the unstructured mesh
umesh = None
for m in sp.meshes.values():
if isinstance(m, openmc.UnstructuredMesh):
umesh = m
assert umesh is not None
# check that the first element centroid is correct
# this will depend on whether the tet mesh or hex mesh
# file is being used in this test
if umesh.element_types[0] == umesh._LINEAR_TET:
exp_vertex = (-10.0, -10.0, -10.0)
exp_centroid = (-8.75, -9.75, -9.25)
else:
exp_vertex = (-10.0, -10.0, 10.0)
exp_centroid = (-9.0, -9.0, 9.0)
np.testing.assert_array_equal(umesh.vertices[0], exp_vertex)
np.testing.assert_array_equal(umesh.centroid(0), exp_centroid)
# loop over the tallies and get data
for tally in sp.tallies.values():
# find the regular and unstructured meshes
if tally.contains_filter(openmc.MeshFilter):
flt = tally.find_filter(openmc.MeshFilter)
if isinstance(flt.mesh, openmc.RegularMesh):
reg_mesh_data = self.get_mesh_tally_data(tally)
if self.holes:
reg_mesh_data = np.delete(reg_mesh_data, self.holes)
else:
umesh_tally = tally
unstructured_data = self.get_mesh_tally_data(tally, True)
# we expect these results to be the same to within at least ten
# decimal places
decimals = 10 if umesh_tally.estimator == 'collision' else 8
np.testing.assert_array_almost_equal(np.sort(unstructured_data),
np.sort(reg_mesh_data),
decimals)
def get_mesh_tally_data(self, tally, structured=False):
data = tally.get_reshaped_data(value='mean')
if structured:
data = data.reshape((-1, self.ELEM_PER_VOXEL))
else:
data.shape = (data.size, 1)
return np.sum(data, axis=1)
def update_results(self):
"""Update results_true.dat and inputs_true.dat"""
try:
self._build_inputs()
inputs = self._get_inputs()
self._write_inputs(inputs)
self._overwrite_inputs()
self._run_openmc()
self._test_output_created()
finally:
self._cleanup()
def _cleanup(self):
super()._cleanup()
output = glob.glob('tally*.vtk')
output += glob.glob('tally*.e')
for f in output:
if os.path.exists(f):
os.remove(f)
@pytest.fixture
def model():
openmc.reset_auto_ids()
model = openmc.Model()
### Materials ###
materials = openmc.Materials()
fuel_mat = openmc.Material(name="fuel")
fuel_mat.add_nuclide("U235", 1.0)
fuel_mat.set_density('g/cc', 4.5)
materials.append(fuel_mat)
zirc_mat = openmc.Material(name="zircaloy")
zirc_mat.add_element("Zr", 1.0)
zirc_mat.set_density("g/cc", 5.77)
materials.append(zirc_mat)
water_mat = openmc.Material(name="water")
water_mat.add_nuclide("H1", 2.0)
water_mat.add_nuclide("O16", 1.0)
water_mat.set_density("atom/b-cm", 0.07416)
materials.append(water_mat)
model.materials = materials
### Geometry ###
fuel_min_x = openmc.XPlane(-5.0, name="minimum x")
fuel_max_x = openmc.XPlane(5.0, name="maximum x")
fuel_min_y = openmc.YPlane(-5.0, name="minimum y")
fuel_max_y = openmc.YPlane(5.0, name="maximum y")
fuel_min_z = openmc.ZPlane(-5.0, name="minimum z")
fuel_max_z = openmc.ZPlane(5.0, name="maximum z")
fuel_cell = openmc.Cell(name="fuel")
fuel_cell.region = +fuel_min_x & -fuel_max_x & \
+fuel_min_y & -fuel_max_y & \
+fuel_min_z & -fuel_max_z
fuel_cell.fill = fuel_mat
clad_min_x = openmc.XPlane(-6.0, name="minimum x")
clad_max_x = openmc.XPlane(6.0, name="maximum x")
clad_min_y = openmc.YPlane(-6.0, name="minimum y")
clad_max_y = openmc.YPlane(6.0, name="maximum y")
clad_min_z = openmc.ZPlane(-6.0, name="minimum z")
clad_max_z = openmc.ZPlane(6.0, name="maximum z")
clad_cell = openmc.Cell(name="clad")
clad_cell.region = (-fuel_min_x | +fuel_max_x |
-fuel_min_y | +fuel_max_y |
-fuel_min_z | +fuel_max_z) & \
(+clad_min_x & -clad_max_x &
+clad_min_y & -clad_max_y &
+clad_min_z & -clad_max_z)
clad_cell.fill = zirc_mat
# set bounding cell dimension to one
# this will be updated later according to the test case parameters
water_min_x = openmc.XPlane(x0=-1.0,
name="minimum x",
boundary_type='vacuum')
water_max_x = openmc.XPlane(x0=1.0,
name="maximum x",
boundary_type='vacuum')
water_min_y = openmc.YPlane(y0=-1.0,
name="minimum y",
boundary_type='vacuum')
water_max_y = openmc.YPlane(y0=1.0,
name="maximum y",
boundary_type='vacuum')
water_min_z = openmc.ZPlane(z0=-1.0,
name="minimum z",
boundary_type='vacuum')
water_max_z = openmc.ZPlane(z0=1.0,
name="maximum z",
boundary_type='vacuum')
water_cell = openmc.Cell(name="water")
water_cell.region = (-clad_min_x | +clad_max_x |
-clad_min_y | +clad_max_y |
-clad_min_z | +clad_max_z) & \
(+water_min_x & -water_max_x &
+water_min_y & -water_max_y &
+water_min_z & -water_max_z)
water_cell.fill = water_mat
# create a containing universe
model.geometry = openmc.Geometry([fuel_cell, clad_cell, water_cell])
### Reference Tally ###
# create meshes and mesh filters
regular_mesh = openmc.RegularMesh()
regular_mesh.dimension = (10, 10, 10)
regular_mesh.lower_left = (-10.0, -10.0, -10.0)
regular_mesh.upper_right = (10.0, 10.0, 10.0)
regular_mesh_filter = openmc.MeshFilter(mesh=regular_mesh)
regular_mesh_tally = openmc.Tally(name="regular mesh tally")
regular_mesh_tally.filters = [regular_mesh_filter]
regular_mesh_tally.scores = ['flux']
model.tallies = openmc.Tallies([regular_mesh_tally])
### Settings ###
settings = openmc.Settings()
settings.run_mode = 'fixed source'
settings.particles = 1000
settings.batches = 10
# source setup
r = openmc.stats.Uniform(a=0.0, b=0.0)
cos_theta = openmc.stats.Discrete(x=[1.0], p=[1.0])
phi = openmc.stats.Discrete(x=[0.0], p=[1.0])
space = openmc.stats.SphericalIndependent(r, cos_theta, phi)
energy = openmc.stats.Discrete(x=[15.e+06], p=[1.0])
source = openmc.IndependentSource(space=space, energy=energy)
settings.source = source
model.settings = settings
return model
param_values = (['libmesh', 'moab'], # mesh libraries
['collision', 'tracklength'], # estimators
[True, False], # geometry outside of the mesh
[(333, 90, 77), None]) # location of holes in the mesh
test_cases = []
for i, (lib, estimator, ext_geom, holes) in enumerate(product(*param_values)):
test_cases.append({'library' : lib,
'estimator' : estimator,
'external_geom' : ext_geom,
'holes' : holes,
'inputs_true' : 'inputs_true{}.dat'.format(i)})
@pytest.mark.parametrize("test_opts", test_cases)
def test_unstructured_mesh_tets(model, test_opts):
# skip the test if the library is not enabled
if test_opts['library'] == 'moab' and not openmc.lib._dagmc_enabled():
pytest.skip("DAGMC (and MOAB) mesh not enabled in this build.")
if test_opts['library'] == 'libmesh' and not openmc.lib._libmesh_enabled():
pytest.skip("LibMesh is not enabled in this build.")
# skip the tracklength test for libmesh
if test_opts['library'] == 'libmesh' and \
test_opts['estimator'] == 'tracklength':
pytest.skip("Tracklength tallies are not supported using libmesh.")
if test_opts['holes']:
mesh_filename = "test_mesh_tets_w_holes.e"
else:
mesh_filename = "test_mesh_tets.e"
# add reference mesh tally
regular_mesh_tally = model.tallies[0]
regular_mesh_tally.estimator = test_opts['estimator']
# add analagous unstructured mesh tally
uscd_mesh = openmc.UnstructuredMesh(mesh_filename, test_opts['library'])
if test_opts['library'] == 'moab':
uscd_mesh.options = 'MAX_DEPTH=15;PLANE_SET=2'
uscd_filter = openmc.MeshFilter(mesh=uscd_mesh)
# create tallies
uscd_tally = openmc.Tally(name="unstructured mesh tally")
uscd_tally.filters = [uscd_filter]
uscd_tally.scores = ['flux']
uscd_tally.estimator = test_opts['estimator']
model.tallies.append(uscd_tally)
# modify model geometry according to test opts
if test_opts['external_geom']:
scale_factor = 15.0
else:
scale_factor = 10.0
harness = UnstructuredMeshTest('statepoint.10.h5',
model,
test_opts['inputs_true'],
test_opts['holes'],
scale_factor)
harness.main()
@pytest.mark.skipif(not openmc.lib._libmesh_enabled(),
reason='LibMesh is not enabled in this build.')
def test_unstructured_mesh_hexes(model):
regular_mesh_tally = model.tallies[0]
regular_mesh_tally.estimator = 'collision'
# add analagous unstructured mesh tally
uscd_mesh = openmc.UnstructuredMesh('test_mesh_hexes.e', 'libmesh')
uscd_filter = openmc.MeshFilter(mesh=uscd_mesh)
# create tallies
uscd_tally = openmc.Tally(name="unstructured mesh tally")
uscd_tally.filters = [uscd_filter]
uscd_tally.scores = ['flux']
uscd_tally.estimator = 'collision'
model.tallies.append(uscd_tally)
harness = UnstructuredMeshTest('statepoint.10.h5',
model)
harness.ELEM_PER_VOXEL = 1
harness.main()