Merge pull request #6 from fusion-energy/adding_ci

added ci and tests

.github/workflows/ci.yml

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+
+name: CI with install
+
+on:
+  pull_request:
+    branches:
+      - develop
+      - main
+
+jobs:
+  testing:
+    runs-on: ubuntu-latest
+    container:
+      image: docker pull continuumio/miniconda3
+    steps:
+      - name: Checkout repository
+        uses: actions/checkout@v3
+
+      - name: install dependencies
+        run: |
+          conda install -c conda-forge mamba
+          mamba install -c cadquery -c conda-forge moab gmsh python-gmsh cadquery=master -y
+
+      - name: install package with tests
+        run: |
+          pip install .
+
+      - name: Run tests
+        run: |
+          pytest tests

tests/test_csg_cad_cuboid.py

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+from model_benchmark_zoo import Cuboid
+import openmc
+import math
+
+def test_comparing():
+    # single material used in both simulations
+    mat1 = openmc.Material(name='1')
+    mat1.add_nuclide('Fe56', 1)
+    mat1.set_density('g/cm3', 1)
+    my_materials = openmc.Materials([mat1])
+
+    # geometry used in both simulations
+    common_geometry_object = Cuboid(materials=my_materials, width=10)
+    # just writing a CAD step file for visulisation
+    common_geometry_object.export_stp_file("cuboid.stp")
+
+    mat_filter = openmc.MaterialFilter(mat1)
+    tally = openmc.Tally(name='mat1_flux_tally')
+    tally.filters = [mat_filter]
+    tally.scores = ['flux']
+    my_tallies = openmc.Tallies([tally])
+
+    my_settings = openmc.Settings()
+    my_settings.batches = 10
+    my_settings.inactive = 0
+    my_settings.particles = 500
+    my_settings.run_mode = 'fixed source'
+
+    # Create a DT point source
+    my_source = openmc.Source()
+    my_source.space = openmc.stats.Point((0, 0, 0))
+    my_source.angle = openmc.stats.Isotropic()
+    my_source.energy = openmc.stats.Discrete([14e6], [1])
+    my_settings.source = my_source
+
+    # making openmc.Model with CSG geometry
+    csg_model = common_geometry_object.csg_model()
+    csg_model.materials = my_materials
+    csg_model.tallies = my_tallies
+    csg_model.settings = my_settings
+
+    output_file_from_csg = csg_model.run()
+
+    # extracting the tally result from the CSG simulation
+    with openmc.StatePoint(output_file_from_csg) as sp_from_csg:
+        csg_result = sp_from_csg.get_tally(name="mat1_flux_tally")
+
+    # making openmc.Model with DAGMC geometry and specifying mesh sizes to get a good representation of a Cuboid
+    dag_model = common_geometry_object.dagmc_model(min_mesh_size=0.01, max_mesh_size=0.5)
+    dag_model.materials = my_materials
+    dag_model.tallies = my_tallies
+    dag_model.settings = my_settings
+
+    output_file_from_cad = dag_model.run()
+
+    # extracting the tally result from the DAGMC simulation
+    with openmc.StatePoint(output_file_from_cad) as sp_from_cad:
+        cad_result = sp_from_cad.get_tally(name="mat1_flux_tally")
+
+    assert math.isclose(cad_result.mean, csg_result.mean)
+

tests/test_csg_cad_sphere.py

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+from model_benchmark_zoo import Sphere
+import openmc
+import math
+
+def test_compare():
+    # single material used in both simulations
+    mat1 = openmc.Material(name='1')
+    mat1.add_nuclide('Fe56', 1)
+    mat1.set_density('g/cm3', 1)
+    my_materials = openmc.Materials([mat1])
+
+    # geometry used in both simulations
+    common_geometry_object = Sphere(materials=my_materials, radius=10)
+    # just writing a CAD step file for visulisation
+    common_geometry_object.export_stp_file("sphere.stp")
+
+    mat_filter = openmc.MaterialFilter(mat1)
+    tally = openmc.Tally(name='mat1_flux_tally')
+    tally.filters = [mat_filter]
+    tally.scores = ['flux']
+    my_tallies = openmc.Tallies([tally])
+
+    my_settings = openmc.Settings()
+    my_settings.batches = 10
+    my_settings.inactive = 0
+    my_settings.particles = 500
+    my_settings.run_mode = 'fixed source'
+
+    # Create a DT point source
+    my_source = openmc.Source()
+    my_source.space = openmc.stats.Point((0, 0, 0))
+    my_source.angle = openmc.stats.Isotropic()
+    my_source.energy = openmc.stats.Discrete([14e6], [1])
+    my_settings.source = my_source
+
+    # making openmc.Model with CSG geometry
+    csg_model = common_geometry_object.csg_model()
+    csg_model.materials = my_materials
+    csg_model.tallies = my_tallies
+    csg_model.settings = my_settings
+
+    output_file_from_csg = csg_model.run()
+
+    # extracting the tally result from the CSG simulation
+    with openmc.StatePoint(output_file_from_csg) as sp_from_csg:
+        csg_result = sp_from_csg.get_tally(name="mat1_flux_tally")
+
+    # making openmc.Model with DAGMC geometry and specifying mesh sizes to get a good representation of a sphere
+    dag_model = common_geometry_object.dagmc_model(min_mesh_size=0.01, max_mesh_size=0.5)
+    dag_model.materials = my_materials
+    dag_model.tallies = my_tallies
+    dag_model.settings = my_settings
+
+    output_file_from_cad = dag_model.run()
+
+    # extracting the tally result from the DAGMC simulation
+    with openmc.StatePoint(output_file_from_cad) as sp_from_cad:
+        cad_result = sp_from_cad.get_tally(name="mat1_flux_tally")
+
+    assert math.isclose(cad_result.mean, csg_result.mean)
+

tests/test_csg_cad_sphericalshell.py

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+from model_benchmark_zoo import SphericalShell
+import openmc
+import math
+
+def test_compare():
+    # single material used in both simulations
+    mat1 = openmc.Material(name='1')
+    mat1.add_nuclide('Fe56', 1)
+    mat1.set_density('g/cm3', 1)
+
+    mat2 = openmc.Material(name='2')
+    mat2.add_nuclide('Be9', 1)
+    mat2.set_density('g/cm3', 1)
+    my_materials = openmc.Materials([mat1, mat2])
+
+    # geometry used in both simulations
+    common_geometry_object = SphericalShell(materials=my_materials, radius1=10, radius2=1)
+    # just writing a CAD step file for visulisation
+    common_geometry_object.export_stp_file("sphericalshell.stp")
+
+    mat1_filter = openmc.MaterialFilter(mat1)
+    tally1 = openmc.Tally(name='mat1_flux_tally')
+    tally1.filters = [mat1_filter]
+    tally1.scores = ['flux']
+
+    mat2_filter = openmc.MaterialFilter(mat2)
+    tally2 = openmc.Tally(name='mat2_flux_tally')
+    tally2.filters = [mat2_filter]
+    tally2.scores = ['flux']
+
+    my_tallies = openmc.Tallies([tally1, tally2])
+
+    my_settings = openmc.Settings()
+    my_settings.batches = 10
+    my_settings.inactive = 0
+    my_settings.particles = 500
+    my_settings.run_mode = 'fixed source'
+
+    # Create a DT point source
+    my_source = openmc.Source()
+    my_source.space = openmc.stats.Point((0, 0, 0))
+    my_source.angle = openmc.stats.Isotropic()
+    my_source.energy = openmc.stats.Discrete([14e6], [1])
+    my_settings.source = my_source
+
+    # making openmc.Model with CSG geometry
+    csg_model = common_geometry_object.csg_model()
+    csg_model.materials = my_materials
+    csg_model.tallies = my_tallies
+    csg_model.settings = my_settings
+
+    output_file_from_csg = csg_model.run()
+
+    # extracting the tally result from the CSG simulation
+    with openmc.StatePoint(output_file_from_csg) as sp_from_csg:
+        csg_result_mat_1 = sp_from_csg.get_tally(name="mat1_flux_tally")
+        csg_result_mat_2 = sp_from_csg.get_tally(name="mat2_flux_tally")
+    csg_result_mat_1_str = f'CSG tally mean {csg_result_mat_1.mean} std dev {csg_result_mat_1.std_dev}'
+    csg_result_mat_2_str = f'CSG tally mean {csg_result_mat_1.mean} std dev {csg_result_mat_1.std_dev}'
+
+    # making openmc.Model with DAGMC geometry and specifying mesh sizes to get a good representation of a sphere
+    dag_model = common_geometry_object.dagmc_model(min_mesh_size=0.01, max_mesh_size=0.5)
+    dag_model.materials = my_materials
+    dag_model.tallies = my_tallies
+    dag_model.settings = my_settings
+
+    output_file_from_cad = dag_model.run()
+
+    # extracting the tally result from the DAGMC simulation
+    with openmc.StatePoint(output_file_from_cad) as sp_from_cad:
+        cad_result_mat_1 = sp_from_cad.get_tally(name="mat1_flux_tally")
+        cad_result_mat_2 = sp_from_cad.get_tally(name="mat2_flux_tally")
+
+    assert math.isclose(cad_result_mat_1.mean, csg_result_mat_1.mean)
+    assert math.isclose(cad_result_mat_2.mean, csg_result_mat_2.mean)

tests/test_csg_cad_two_touching_cuboids.py

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+from model_benchmark_zoo import TwoTouchingCuboids
+import openmc
+import math
+
+def test_compare():
+    # materials used in both simulations
+    mat1 = openmc.Material(name='1')
+    mat1.add_nuclide('Fe56', 1)
+    mat1.set_density('g/cm3', 1)
+    mat2 = openmc.Material(name='2')
+    mat2.add_nuclide('Fe56', 1)
+    mat2.set_density('g/cm3', 1)
+    my_materials = openmc.Materials([mat1, mat2])
+
+    # geometry used in both simulations
+    common_geometry_object = TwoTouchingCuboids(
+        materials=my_materials, width1=10, width2=4)
+    # just writing a CAD step file for visulisation
+    common_geometry_object.export_stp_file("TwoTouchingCuboids.stp")
+
+    mat1_filter = openmc.MaterialFilter(mat1)
+    tally1 = openmc.Tally(name='mat1_flux_tally')
+    tally1.filters = [mat1_filter]
+    tally1.scores = ['flux']
+
+    mat2_filter = openmc.MaterialFilter(mat2)
+    tally2 = openmc.Tally(name='mat2_flux_tally')
+    tally2.filters = [mat2_filter]
+    tally2.scores = ['flux']
+    my_tallies = openmc.Tallies([tally1, tally2])
+
+    my_settings = openmc.Settings()
+    my_settings.batches = 10
+    my_settings.inactive = 0
+    my_settings.particles = 500
+    my_settings.run_mode = 'fixed source'
+
+    # Create a DT point source
+    my_source = openmc.Source()
+    my_source.space = openmc.stats.Point((0, 0, 0))
+    my_source.angle = openmc.stats.Isotropic()
+    my_source.energy = openmc.stats.Discrete([14e6], [1])
+    my_settings.source = my_source
+
+    # making openmc.Model with CSG geometry
+    csg_model = common_geometry_object.csg_model()
+    csg_model.materials = my_materials
+    csg_model.tallies = my_tallies
+    csg_model.settings = my_settings
+
+    output_file_from_csg = csg_model.run()
+
+    # extracting the tally result from the CSG simulation
+    with openmc.StatePoint(output_file_from_csg) as sp_from_csg:
+        csg_result1 = sp_from_csg.get_tally(name="mat1_flux_tally")
+        csg_result2 = sp_from_csg.get_tally(name="mat2_flux_tally")
+
+    # making openmc.Model with DAGMC geometry and specifying mesh sizes to get a good representation of a TwoTouchingCuboids
+    dag_model = common_geometry_object.dagmc_model(min_mesh_size=0.01, max_mesh_size=0.5)
+    dag_model.materials = my_materials
+    dag_model.tallies = my_tallies
+    dag_model.settings = my_settings
+
+    output_file_from_cad = dag_model.run()
+
+    # extracting the tally result from the DAGMC simulation
+    with openmc.StatePoint(output_file_from_cad) as sp_from_cad:
+        cad_result1 = sp_from_cad.get_tally(name="mat1_flux_tally")
+        cad_result2 = sp_from_cad.get_tally(name="mat2_flux_tally")
+
+    assert math.isclose(cad_result1.mean, csg_result1.mean)
+    assert math.isclose(cad_result2.mean, csg_result2.mean)