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OpenMC/tests/regression_tests/surface_source_write/test.py
Paul Romano 55b52b7ef3
Release of version 0.15.0 (#3050)
2024-06-22 01:28:56 +00:00

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"""Test the 'surface_source_write' setting.
Results
-------
All results are generated using only 1 MPI process.
All results are generated using 1 thread except for "test_consistency_low_realization_number".
This specific test verifies that when the number of realization (i.e., point being candidate
to be stored) is lower than the capacity, results are reproducible even with multiple
threads (i.e., there is no potential thread competition that would produce different
results in that case).
All results are generated using the history-based mode except for cases e01 to e03.
All results are visually verified using the '_visualize.py' script in the regression test folder.
OpenMC models
-------------
Four OpenMC models with CSG-only geometries are used to cover the transmission, vacuum,
reflective and periodic Boundary Conditions (BC):
- model_1: cylindrical core in 2 boxes (vacuum and transmission BC),
- model_2: cylindrical core in 1 box (vacuum BC),
- model_3: cylindrical core in 1 box (reflective BC),
- model_4: cylindrical core in 1 box (periodic BC).
Two models including DAGMC geometries are also used, based on the mesh file 'dagmc.h5m'
available from tests/regression_tests/dagmc/legacy:
- model_dagmc_1: model adapted from tests/regression_tests/dagmc/legacy,
- model_dagmc_2: model_dagmc_1 contained in two CSG boxes to introduce multiple level of coordinates.
Test cases
----------
Test cases using CSG-only geometries:
======== ======= ========= ========================= ===== ===================================
Folder Model Surface Cell BC* Expected particles
======== ======= ========= ========================= ===== ===================================
case-01 model_1 No No T+V Particles crossing any surface in
the model
case-02 model_1 1 No T Particles crossing this surface
only
case-03 model_1 Multiple No T Particles crossing the declared
surfaces
case-04 model_1 Multiple cell (lower universe) T Particles crossing the declared
surfaces that come from or are
coming to the cell
case-05 model_1 Multiple cell (root universe) T Particles crossing the declared
surfaces that come from or are
coming to the cell
case-06 model_1 No cell (lower universe) T Particles crossing any surface that
come from or are coming to the cell
case-07 model_1 No cell (root universe) T Particles crossing any surface that
come from or are coming to the cell
case-08 model_1 No cellfrom (lower universe) T Particles crossing any surface that
come from the cell
case-09 model_1 No cellto (lower universe) T Particles crossing any surface that
are coming to the cell
case-10 model_1 No cellfrom (root universe) T Particles crossing any surface that
come from the cell
case-11 model_1 No cellto (root universe) T Particles crossing any surface that
are coming to the cell
case-12 model_2 Multiple No V Particles crossing the declared
surfaces
case-13 model_2 Multiple cell (root universe) V Particles crossing any surface that
come from or are coming to the cell
case-14 model_2 Multiple cellfrom (root universe) V Particles crossing any surface that
are coming to the cell
case-15 model_2 Multiple cellto (root universe) V None
case-16 model_3 Multiple No R Particles crossing the declared
surfaces
case-17 model_3 Multiple cell (root universe) R None
case-18 model_3 Multiple cellfrom (root universe) R None
case-19 model_3 Multiple cellto (root universe) R None
case-20 model_4 1 No P+R Particles crossing the declared
periodic surface
case-21 model_4 1 cell (root universe) P+R None
======== ======= ========= ========================= ===== ===================================
*: BC stands for Boundary Conditions, T for Transmission, R for Reflective, and V for Vacuum.
An additional case, called 'case-a01', is used to check that the results are comparable when
the number of threads is set to 2 if the number of realization is lower than the capacity.
Cases e01 to e03 are the event-based cases corresponding to the history-based cases 04, 07 and 13,
respectively.
Test cases using DAGMC geometries:
======== ============= ========= ===================== ===== ===================================
Folder Model Surface Cell BC* Expected particles
======== ============= ========= ===================== ===== ===================================
case-d01 model_dagmc_1 No No T+V Particles crossing any surface in
the model
case-d02 model_dagmc_1 1 No T Particles crossing this surface
only
case-d03 model_dagmc_1 No cell T Particles crossing any surface that
come from or are coming to the cell
case-d04 model_dagmc_1 1 cell T Particles crossing the declared
surface that come from or are
coming to the cell
case-d05 model_dagmc_1 No cellfrom T Particles crossing any surface that
come from the cell
case-d06 model_dagmc_1 No cellto T Particles crossing any surface that
are coming to the cell
case-d07 model_dagmc_2 Multiple cell (lower universe) T Particles crossing the declared
surfaces that come from or are
coming to the cell
case-d08 model_dagmc_2 Multiple cell (root universe) T Particles crossing the declared
surfaces that come from or are
coming to the cell
======== ============= ========= ===================== ===== ===================================
*: BC stands for Boundary Conditions, T for Transmission, and V for Vacuum.
Notes:
- The test cases list is non-exhaustive compared to the number of possible combinations.
Test cases have been selected based on use and internal code logic.
- Cases 08 to 11 are testing that the feature still works even if the level of coordinates
before and after crossing a surface is different,
- Tests on boundary conditions are not performed on DAGMC models as the logic is shared
with CSG-only models,
- Cases that should return an error are tested in the 'test_exceptions' unit test
from 'unit_tests/surface_source_write/test.py'.
TODO:
- Test with a lattice.
"""
import os
import shutil
from pathlib import Path
import h5py
import numpy as np
import openmc
import openmc.lib
import pytest
from tests.testing_harness import PyAPITestHarness
from tests.regression_tests import config
@pytest.fixture(scope="function")
def single_thread(monkeypatch):
"""Set the number of OMP threads to 1 for the test."""
monkeypatch.setenv("OMP_NUM_THREADS", "1")
@pytest.fixture(scope="function")
def two_threads(monkeypatch):
"""Set the number of OMP threads to 2 for the test."""
monkeypatch.setenv("OMP_NUM_THREADS", "2")
@pytest.fixture(scope="function")
def single_process(monkeypatch):
"""Set the number of MPI process to 1 for the test."""
monkeypatch.setitem(config, "mpi_np", "1")
@pytest.fixture(scope="module")
def model_1():
"""Cylindrical core contained in a first box which is contained in a larger box.
A lower universe is used to describe the interior of the first box which
contains the core and its surrounding space.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
fuel = openmc.Material()
fuel.add_nuclide("U234", 0.0004524)
fuel.add_nuclide("U235", 0.0506068)
fuel.add_nuclide("U238", 0.9487090)
fuel.add_nuclide("U236", 0.0002318)
fuel.add_nuclide("O16", 2.0)
fuel.set_density("g/cm3", 11.0)
water = openmc.Material()
water.add_nuclide("H1", 2.0)
water.add_nuclide("O16", 1.0)
water.set_density("g/cm3", 1.0)
# =============================================================================
# Geometry
# =============================================================================
# -----------------------------------------------------------------------------
# Cylindrical core
# -----------------------------------------------------------------------------
# Parameters
core_radius = 2.0
core_height = 4.0
# Surfaces
core_cylinder = openmc.ZCylinder(r=core_radius)
core_lower_plane = openmc.ZPlane(-core_height / 2.0)
core_upper_plane = openmc.ZPlane(core_height / 2.0)
# Region
core_region = -core_cylinder & +core_lower_plane & -core_upper_plane
# Cells
core = openmc.Cell(fill=fuel, region=core_region)
outside_core_region = +core_cylinder | -core_lower_plane | +core_upper_plane
outside_core = openmc.Cell(fill=water, region=outside_core_region)
# Universe
inside_box1_universe = openmc.Universe(cells=[core, outside_core])
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 6.0
# Surfaces
box1_rpp = openmc.model.RectangularParallelepiped(
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
)
# Cell
box1 = openmc.Cell(fill=inside_box1_universe, region=-box1_rpp)
# -----------------------------------------------------------------------------
# Box 2
# -----------------------------------------------------------------------------
# Parameters
box2_size = 8
# Surfaces
box2_rpp = openmc.model.RectangularParallelepiped(
-box2_size / 2.0, box2_size / 2.0,
-box2_size / 2.0, box2_size / 2.0,
-box2_size / 2.0, box2_size / 2.0,
boundary_type="vacuum"
)
# Cell
box2 = openmc.Cell(fill=water, region=-box2_rpp & +box1_rpp)
# Register geometry
model.geometry = openmc.Geometry([box1, box2])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
bounds = [
-core_radius,
-core_radius,
-core_height / 2.0,
core_radius,
core_radius,
core_height / 2.0,
]
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
model.settings.source = openmc.IndependentSource(
space=distribution, constraints={'fissionable': True})
return model
@pytest.fixture
def model_2():
"""Cylindrical core contained in a box.
A lower universe is used to describe the interior of the box which
contains the core and its surrounding space.
The box is defined with vacuum boundary conditions.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
fuel = openmc.Material()
fuel.add_nuclide("U234", 0.0004524)
fuel.add_nuclide("U235", 0.0506068)
fuel.add_nuclide("U238", 0.9487090)
fuel.add_nuclide("U236", 0.0002318)
fuel.add_nuclide("O16", 2.0)
fuel.set_density("g/cm3", 11.0)
water = openmc.Material()
water.add_nuclide("H1", 2.0)
water.add_nuclide("O16", 1.0)
water.set_density("g/cm3", 1.0)
# =============================================================================
# Geometry
# =============================================================================
# -----------------------------------------------------------------------------
# Cylindrical core
# -----------------------------------------------------------------------------
# Parameters
core_radius = 2.0
core_height = 4.0
# Surfaces
core_cylinder = openmc.ZCylinder(r=core_radius)
core_lower_plane = openmc.ZPlane(-core_height / 2.0)
core_upper_plane = openmc.ZPlane(core_height / 2.0)
# Region
core_region = -core_cylinder & +core_lower_plane & -core_upper_plane
# Cells
core = openmc.Cell(fill=fuel, region=core_region)
outside_core_region = +core_cylinder | -core_lower_plane | +core_upper_plane
outside_core = openmc.Cell(fill=water, region=outside_core_region)
# Universe
inside_box1_universe = openmc.Universe(cells=[core, outside_core])
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 6.0
# Surfaces
box1_rpp = openmc.model.RectangularParallelepiped(
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
boundary_type="vacuum"
)
# Cell
box1 = openmc.Cell(fill=inside_box1_universe, region=-box1_rpp)
# Register geometry
model.geometry = openmc.Geometry([box1])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
bounds = [
-core_radius,
-core_radius,
-core_height / 2.0,
core_radius,
core_radius,
core_height / 2.0,
]
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
model.settings.source = openmc.IndependentSource(
space=distribution, constraints={'fissionable': True})
return model
@pytest.fixture
def model_3():
"""Cylindrical core contained in a box.
A lower universe is used to describe the interior of the box which
contains the core and its surrounding space.
The box is defined with reflective boundary conditions.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
fuel = openmc.Material()
fuel.add_nuclide("U234", 0.0004524)
fuel.add_nuclide("U235", 0.0506068)
fuel.add_nuclide("U238", 0.9487090)
fuel.add_nuclide("U236", 0.0002318)
fuel.add_nuclide("O16", 2.0)
fuel.set_density("g/cm3", 11.0)
water = openmc.Material()
water.add_nuclide("H1", 2.0)
water.add_nuclide("O16", 1.0)
water.set_density("g/cm3", 1.0)
# =============================================================================
# Geometry
# =============================================================================
# -----------------------------------------------------------------------------
# Cylindrical core
# -----------------------------------------------------------------------------
# Parameters
core_radius = 2.0
core_height = 4.0
# Surfaces
core_cylinder = openmc.ZCylinder(r=core_radius)
core_lower_plane = openmc.ZPlane(-core_height / 2.0)
core_upper_plane = openmc.ZPlane(core_height / 2.0)
# Region
core_region = -core_cylinder & +core_lower_plane & -core_upper_plane
# Cells
core = openmc.Cell(fill=fuel, region=core_region)
outside_core_region = +core_cylinder | -core_lower_plane | +core_upper_plane
outside_core = openmc.Cell(fill=water, region=outside_core_region)
# Universe
inside_box1_universe = openmc.Universe(cells=[core, outside_core])
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 6.0
# Surfaces
box1_rpp = openmc.model.RectangularParallelepiped(
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
boundary_type="reflective"
)
# Cell
box1 = openmc.Cell(fill=inside_box1_universe, region=-box1_rpp)
# Register geometry
model.geometry = openmc.Geometry([box1])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
bounds = [
-core_radius,
-core_radius,
-core_height / 2.0,
core_radius,
core_radius,
core_height / 2.0,
]
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
model.settings.source = openmc.IndependentSource(
space=distribution, constraints={'fissionable': True})
return model
@pytest.fixture
def model_4():
"""Cylindrical core contained in a box.
A lower universe is used to describe the interior of the box which
contains the core and its surrounding space.
The box is defined with a pair of periodic boundary with reflective
boundaries.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
fuel = openmc.Material()
fuel.add_nuclide("U234", 0.0004524)
fuel.add_nuclide("U235", 0.0506068)
fuel.add_nuclide("U238", 0.9487090)
fuel.add_nuclide("U236", 0.0002318)
fuel.add_nuclide("O16", 2.0)
fuel.set_density("g/cm3", 11.0)
water = openmc.Material()
water.add_nuclide("H1", 2.0)
water.add_nuclide("O16", 1.0)
water.set_density("g/cm3", 1.0)
# =============================================================================
# Geometry
# =============================================================================
# -----------------------------------------------------------------------------
# Cylindrical core
# -----------------------------------------------------------------------------
# Parameters
core_radius = 2.0
core_height = 4.0
# Surfaces
core_cylinder = openmc.ZCylinder(r=core_radius)
core_lower_plane = openmc.ZPlane(-core_height / 2.0)
core_upper_plane = openmc.ZPlane(core_height / 2.0)
# Region
core_region = -core_cylinder & +core_lower_plane & -core_upper_plane
# Cells
core = openmc.Cell(fill=fuel, region=core_region)
outside_core_region = +core_cylinder | -core_lower_plane | +core_upper_plane
outside_core = openmc.Cell(fill=water, region=outside_core_region)
# Universe
inside_box1_universe = openmc.Universe(cells=[core, outside_core])
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 6.0
# Surfaces
box1_lower_plane = openmc.ZPlane(-box1_size / 2.0, boundary_type="periodic")
box1_upper_plane = openmc.ZPlane(box1_size / 2.0, boundary_type="periodic")
box1_left_plane = openmc.XPlane(-box1_size / 2.0, boundary_type="reflective")
box1_right_plane = openmc.XPlane(box1_size / 2.0, boundary_type="reflective")
box1_rear_plane = openmc.YPlane(-box1_size / 2.0, boundary_type="reflective")
box1_front_plane = openmc.YPlane(box1_size / 2.0, boundary_type="reflective")
# Region
box1_region = (
+box1_lower_plane
& -box1_upper_plane
& +box1_left_plane
& -box1_right_plane
& +box1_rear_plane
& -box1_front_plane
)
# Cell
box1 = openmc.Cell(fill=inside_box1_universe, region=box1_region)
# Register geometry
model.geometry = openmc.Geometry([box1])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
bounds = [
-core_radius,
-core_radius,
-core_height / 2.0,
core_radius,
core_radius,
core_height / 2.0,
]
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
model.settings.source = openmc.IndependentSource(
space=distribution, constraints={'fissionable': True})
return model
def return_surface_source_data(filepath):
"""Read a surface source file and return a sorted array composed
of flatten arrays of source data for each surface source point.
TODO:
- use read_source_file from source.py instead. Or a dedicated function
to produce sorted list of source points for a given file.
Parameters
----------
filepath : str
Path to the surface source file
Returns
-------
data : np.array
Sorted array composed of flatten arrays of source data for
each surface source point
"""
data = []
keys = []
# Read source file
with h5py.File(filepath, "r") as f:
for point in f["source_bank"]:
r = point["r"]
u = point["u"]
e = point["E"]
time = point["time"]
wgt = point["wgt"]
delayed_group = point["delayed_group"]
surf_id = point["surf_id"]
particle = point["particle"]
key = (
f"{r[0]:.10e} {r[1]:.10e} {r[2]:.10e} {u[0]:.10e} {u[1]:.10e} {u[2]:.10e}"
f"{e:.10e} {time:.10e} {wgt:.10e} {delayed_group} {surf_id} {particle}"
)
keys.append(key)
values = [*r, *u, e, time, wgt, delayed_group, surf_id, particle]
assert len(values) == 12
data.append(values)
data = np.array(data)
keys = np.array(keys)
sorted_idx = np.argsort(keys)
return data[sorted_idx]
class SurfaceSourceWriteTestHarness(PyAPITestHarness):
def __init__(self, statepoint_name, model=None, inputs_true=None, workdir=None):
super().__init__(statepoint_name, model, inputs_true)
self.workdir = workdir
def _test_output_created(self):
"""Make sure surface_source.h5 has also been created."""
super()._test_output_created()
if self._model.settings.surf_source_write:
assert os.path.exists(
"surface_source.h5"
), "Surface source file has not been created."
def _compare_output(self):
"""Compare surface_source.h5 files."""
if self._model.settings.surf_source_write:
source_true = return_surface_source_data("surface_source_true.h5")
source_test = return_surface_source_data("surface_source.h5")
np.testing.assert_allclose(source_true, source_test, rtol=1e-07)
def main(self):
"""Accept commandline arguments and either run or update tests."""
if config["build_inputs"]:
self.build_inputs()
elif config["update"]:
self.update_results()
else:
self.execute_test()
def build_inputs(self):
"""Build inputs."""
base_dir = os.getcwd()
try:
os.chdir(self.workdir)
self._build_inputs()
finally:
os.chdir(base_dir)
def execute_test(self):
"""Build inputs, run OpenMC, and verify correct results."""
base_dir = os.getcwd()
try:
os.chdir(self.workdir)
self._build_inputs()
inputs = self._get_inputs()
self._write_inputs(inputs)
self._compare_inputs()
self._run_openmc()
self._test_output_created()
self._compare_output()
results = self._get_results()
self._write_results(results)
self._compare_results()
finally:
self._cleanup()
os.chdir(base_dir)
def update_results(self):
"""Update results_true.dat and inputs_true.dat"""
base_dir = os.getcwd()
try:
os.chdir(self.workdir)
self._build_inputs()
inputs = self._get_inputs()
self._write_inputs(inputs)
self._overwrite_inputs()
self._run_openmc()
self._test_output_created()
results = self._get_results()
self._write_results(results)
self._overwrite_results()
finally:
self._cleanup()
os.chdir(base_dir)
def _overwrite_results(self):
"""Also add the 'surface_source.h5' file during overwriting."""
super()._overwrite_results()
if os.path.exists("surface_source.h5"):
shutil.copyfile("surface_source.h5", "surface_source_true.h5")
def _cleanup(self):
"""Also remove the 'surface_source.h5' file while cleaning."""
super()._cleanup()
fs = "surface_source.h5"
if os.path.exists(fs):
os.remove(fs)
@pytest.mark.skipif(config["event"] is True, reason="Results from history-based mode.")
@pytest.mark.parametrize(
"folder, model_name, parameter",
[
("case-01", "model_1", {"max_particles": 300}),
("case-02", "model_1", {"max_particles": 300, "surface_ids": [8]}),
(
"case-03",
"model_1",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9]},
),
(
"case-04",
"model_1",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 2},
),
(
"case-05",
"model_1",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 3},
),
("case-06", "model_1", {"max_particles": 300, "cell": 2}),
("case-07", "model_1", {"max_particles": 300, "cell": 3}),
("case-08", "model_1", {"max_particles": 300, "cellfrom": 2}),
("case-09", "model_1", {"max_particles": 300, "cellto": 2}),
("case-10", "model_1", {"max_particles": 300, "cellfrom": 3}),
("case-11", "model_1", {"max_particles": 300, "cellto": 3}),
(
"case-12",
"model_2",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9]},
),
(
"case-13",
"model_2",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 3},
),
(
"case-14",
"model_2",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cellfrom": 3},
),
(
"case-15",
"model_2",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cellto": 3},
),
(
"case-16",
"model_3",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9]},
),
(
"case-17",
"model_3",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 3},
),
(
"case-18",
"model_3",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cellfrom": 3},
),
(
"case-19",
"model_3",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cellto": 3},
),
(
"case-20",
"model_4",
{"max_particles": 300, "surface_ids": [4]},
),
(
"case-21",
"model_4",
{"max_particles": 300, "surface_ids": [4], "cell": 3},
),
],
)
def test_surface_source_cell_history_based(
folder, model_name, parameter, single_thread, single_process, request
):
"""Test on history-based results for CSG-only geometries."""
assert os.environ["OMP_NUM_THREADS"] == "1"
assert config["mpi_np"] == "1"
model = request.getfixturevalue(model_name)
model.settings.surf_source_write = parameter
harness = SurfaceSourceWriteTestHarness(
"statepoint.5.h5", model=model, workdir=folder
)
harness.main()
@pytest.mark.skipif(config["event"] is True, reason="Results from history-based mode.")
def test_consistency_low_realization_number(model_1, two_threads, single_process):
"""The objective is to test that the results produced, in a case where
the number of potential realization (particle storage) is low
compared to the capacity of storage, are still consistent.
This configuration ensures that the competition between threads does not
occur and that the content of the source file created can be compared.
"""
assert os.environ["OMP_NUM_THREADS"] == "2"
assert config["mpi_np"] == "1"
model_1.settings.surf_source_write = {
"max_particles": 200,
"surface_ids": [1, 2, 3],
"cellfrom": 2,
}
harness = SurfaceSourceWriteTestHarness(
"statepoint.5.h5", model=model_1, workdir="case-a01"
)
harness.main()
@pytest.mark.skipif(config["event"] is False, reason="Results from event-based mode.")
@pytest.mark.parametrize(
"folder, model_name, parameter",
[
(
"case-e01",
"model_1",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 2},
),
("case-e02", "model_1", {"max_particles": 300, "cell": 3}),
(
"case-e03",
"model_2",
{"max_particles": 300, "surface_ids": [4, 5, 6, 7, 8, 9], "cell": 3},
),
],
)
def test_surface_source_cell_event_based(
folder, model_name, parameter, single_thread, single_process, request
):
"""Test on event-based results for CSG-only geometries."""
assert os.environ["OMP_NUM_THREADS"] == "1"
assert config["mpi_np"] == "1"
model = request.getfixturevalue(model_name)
model.settings.surf_source_write = parameter
harness = SurfaceSourceWriteTestHarness(
"statepoint.5.h5", model=model, workdir=folder
)
harness.main()
@pytest.fixture(scope="module")
def model_dagmc_1():
"""Model based on the mesh file 'dagmc.h5m' available from
tests/regression_tests/dagmc/legacy.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
u235 = openmc.Material(name="no-void fuel")
u235.add_nuclide("U235", 1.0, "ao")
u235.set_density("g/cc", 11)
u235.id = 40
water = openmc.Material(name="water")
water.add_nuclide("H1", 2.0, "ao")
water.add_nuclide("O16", 1.0, "ao")
water.set_density("g/cc", 1.0)
water.add_s_alpha_beta("c_H_in_H2O")
water.id = 41
materials = openmc.Materials([u235, water])
model.materials = materials
# =============================================================================
# Geometry
# =============================================================================
dagmc_univ = openmc.DAGMCUniverse(Path("../../dagmc/legacy/dagmc.h5m"))
model.geometry = openmc.Geometry(dagmc_univ)
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20])
model.settings.source = openmc.IndependentSource(
space=source_box, constraints={'fissionable': True})
return model
@pytest.fixture(scope="module")
def model_dagmc_2():
"""Model based on the mesh file 'dagmc.h5m' available from
tests/regression_tests/dagmc/legacy.
This model corresponds to the model_dagmc_1 contained in two boxes to introduce
multiple level of coordinates from CSG geometry.
"""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
u235 = openmc.Material(name="no-void fuel")
u235.add_nuclide("U235", 1.0, "ao")
u235.set_density("g/cc", 11)
u235.id = 40
water = openmc.Material(name="water")
water.add_nuclide("H1", 2.0, "ao")
water.add_nuclide("O16", 1.0, "ao")
water.set_density("g/cc", 1.0)
water.add_s_alpha_beta("c_H_in_H2O")
water.id = 41
materials = openmc.Materials([u235, water])
model.materials = materials
# =============================================================================
# Geometry
# =============================================================================
dagmc_univ = openmc.DAGMCUniverse(Path("../../dagmc/legacy/dagmc.h5m"))
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 44
# Surfaces
box1_lower_plane = openmc.ZPlane(-box1_size / 2.0, surface_id=101)
box1_upper_plane = openmc.ZPlane(box1_size / 2.0, surface_id=102)
box1_left_plane = openmc.XPlane(-box1_size / 2.0, surface_id=103)
box1_right_plane = openmc.XPlane(box1_size / 2.0, surface_id=104)
box1_rear_plane = openmc.YPlane(-box1_size / 2.0, surface_id=105)
box1_front_plane = openmc.YPlane(box1_size / 2.0, surface_id=106)
# Region
box1_region = (
+box1_lower_plane
& -box1_upper_plane
& +box1_left_plane
& -box1_right_plane
& +box1_rear_plane
& -box1_front_plane
)
# Cell
box1 = openmc.Cell(fill=dagmc_univ, region=box1_region, cell_id=8)
# -----------------------------------------------------------------------------
# Box 2
# -----------------------------------------------------------------------------
# Parameters
box2_size = 48
# Surfaces
box2_lower_plane = openmc.ZPlane(
-box2_size / 2.0, boundary_type="vacuum", surface_id=107
)
box2_upper_plane = openmc.ZPlane(
box2_size / 2.0, boundary_type="vacuum", surface_id=108
)
box2_left_plane = openmc.XPlane(
-box2_size / 2.0, boundary_type="vacuum", surface_id=109
)
box2_right_plane = openmc.XPlane(
box2_size / 2.0, boundary_type="vacuum", surface_id=110
)
box2_rear_plane = openmc.YPlane(
-box2_size / 2.0, boundary_type="vacuum", surface_id=111
)
box2_front_plane = openmc.YPlane(
box2_size / 2.0, boundary_type="vacuum", surface_id=112
)
# Region
inside_box2 = (
+box2_lower_plane
& -box2_upper_plane
& +box2_left_plane
& -box2_right_plane
& +box2_rear_plane
& -box2_front_plane
)
outside_box1 = (
-box1_lower_plane
| +box1_upper_plane
| -box1_left_plane
| +box1_right_plane
| -box1_rear_plane
| +box1_front_plane
)
box2_region = inside_box2 & outside_box1
# Cell
box2 = openmc.Cell(fill=water, region=box2_region, cell_id=9)
# Register geometry
model.geometry = openmc.Geometry([box1, box2])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 100
model.settings.batches = 5
model.settings.inactive = 1
model.settings.seed = 1
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20])
model.settings.source = openmc.IndependentSource(
space=source_box, constraints={'fissionable': True})
return model
@pytest.mark.skipif(
not openmc.lib._dagmc_enabled(), reason="DAGMC CAD geometry is not enabled."
)
@pytest.mark.skipif(config["event"] is True, reason="Results from history-based mode.")
@pytest.mark.parametrize(
"folder, model_name, parameter",
[
("case-d01", "model_dagmc_1", {"max_particles": 300}),
("case-d02", "model_dagmc_1", {"max_particles": 300, "surface_ids": [1]}),
("case-d03", "model_dagmc_1", {"max_particles": 300, "cell": 2}),
(
"case-d04",
"model_dagmc_1",
{"max_particles": 300, "surface_ids": [1], "cell": 2},
),
("case-d05", "model_dagmc_1", {"max_particles": 300, "cellfrom": 2}),
("case-d06", "model_dagmc_1", {"max_particles": 300, "cellto": 2}),
(
"case-d07",
"model_dagmc_2",
{
"max_particles": 300,
"surface_ids": [101, 102, 103, 104, 105, 106],
"cell": 7,
},
),
(
"case-d08",
"model_dagmc_2",
{
"max_particles": 300,
"surface_ids": [101, 102, 103, 104, 105, 106],
"cell": 8,
},
),
],
)
def test_surface_source_cell_dagmc(
folder, model_name, parameter, single_thread, single_process, request
):
"""Test on models with DAGMC geometries."""
assert os.environ["OMP_NUM_THREADS"] == "1"
assert config["mpi_np"] == "1"
model = request.getfixturevalue(model_name)
model.settings.surf_source_write = parameter
harness = SurfaceSourceWriteTestHarness(
"statepoint.5.h5", model=model, workdir=folder
)
harness.main()
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