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Merge pull request #36 from fusion-energy/adding_toka_2
Adding a simple tokamak model
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| Original file line number | Diff line number | Diff line change |
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| name: simple tokamak - cad to dagmc | ||
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| on: | ||
| pull_request: | ||
| branches: | ||
| - develop | ||
| - main | ||
| push: | ||
| branches: | ||
| - main | ||
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| jobs: | ||
| testing: | ||
| runs-on: ubuntu-latest | ||
| steps: | ||
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| - name: checkout actions | ||
| uses: actions/checkout@v4 | ||
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| - name: use upstream test composite action | ||
| uses: ./.github/actions/dependencies_cad_to_dagmc | ||
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| - shell: bash | ||
| env: | ||
| OPENMC_CROSS_SECTIONS: /home/runner/work/model_benchmark_zoo/model_benchmark_zoo/cross_sections.xml | ||
| run: | | ||
| source "${HOME}/conda/etc/profile.d/conda.sh" | ||
| source "${HOME}/conda/etc/profile.d/mamba.sh" | ||
| mamba activate | ||
| pytest tests/test_cad_to_dagmc/test_csg_cad_simple_tokamak.py |
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| Original file line number | Diff line number | Diff line change |
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| @@ -0,0 +1,30 @@ | ||
| name: simple tokamak - cad to openmc | ||
|
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| on: | ||
| pull_request: | ||
| branches: | ||
| - develop | ||
| - main | ||
| push: | ||
| branches: | ||
| - main | ||
|
|
||
| jobs: | ||
| testing: | ||
| runs-on: ubuntu-latest | ||
| steps: | ||
|
|
||
| - name: checkout actions | ||
| uses: actions/checkout@v4 | ||
|
|
||
| - name: use upstream test composite action | ||
| uses: ./.github/actions/dependencies_cad_to_openmc | ||
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| - shell: bash | ||
| env: | ||
| OPENMC_CROSS_SECTIONS: /home/runner/work/model_benchmark_zoo/model_benchmark_zoo/cross_sections.xml | ||
| run: | | ||
| source "${HOME}/conda/etc/profile.d/conda.sh" | ||
| source "${HOME}/conda/etc/profile.d/mamba.sh" | ||
| mamba activate | ||
| pytest tests/test_cad_to_openmc/test_csg_cad_simple_tokamak.py |
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| Original file line number | Diff line number | Diff line change |
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| @@ -0,0 +1,96 @@ | ||
| from model_benchmark_zoo import SimpleTokamak | ||
| import openmc | ||
| import math | ||
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| mat1 = openmc.Material(name='1') | ||
| mat1.add_nuclide('Fe56', 1) | ||
| mat1.set_density('g/cm3', 1) | ||
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| mat2 = openmc.Material(name='2') | ||
| mat2.add_nuclide('Be9', 1) | ||
| mat2.set_density('g/cm3', 1) | ||
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| # geometry used in both simulations | ||
| common_geometry_object = SimpleTokamak( | ||
| radius=500, | ||
| blanket_thicknesses=100, | ||
| center_column_thicknesses=150, | ||
| center_column_extent_beyond_blanket=20, | ||
| ) | ||
| # just writing a CAD step file for visulisation | ||
| common_geometry_object.export_stp_file("simpletokamak.stp") | ||
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| mat1_filter = openmc.MaterialFilter(mat1) | ||
| tally1 = openmc.Tally(name='mat1_flux_tally') | ||
| tally1.filters = [mat1_filter] | ||
| tally1.scores = ['flux'] | ||
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| mat2_filter = openmc.MaterialFilter(mat2) | ||
| tally2 = openmc.Tally(name='mat2_flux_tally') | ||
| tally2.filters = [mat2_filter] | ||
| tally2.scores = ['flux'] | ||
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| my_tallies = openmc.Tallies([tally1, tally2]) | ||
|
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| my_settings = openmc.Settings() | ||
| my_settings.batches = 10 | ||
| my_settings.inactive = 0 | ||
| my_settings.particles = 500 | ||
| my_settings.run_mode = 'fixed source' | ||
|
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||
| # Create a DT ring source | ||
| my_source = openmc.IndependentSource() | ||
| source_r = common_geometry_object.center_column_thicknesses + (common_geometry_object.radius-common_geometry_object.center_column_thicknesses) /2 | ||
| r = openmc.stats.Discrete([source_r], [1]) | ||
| phi = openmc.stats.Uniform(0, 2*math.pi) | ||
| z = openmc.stats.Discrete([0], [1]) | ||
| my_source.space = openmc.stats.CylindricalIndependent(r, phi, z) | ||
| my_source.energy = openmc.stats.Discrete([14e6], [1]) | ||
| my_settings.source = my_source | ||
|
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| # making openmc.Model with CSG geometry | ||
| csg_model = common_geometry_object.csg_model(materials=[mat1, mat2]) | ||
| csg_model.tallies = my_tallies | ||
| csg_model.settings = my_settings | ||
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| output_file_from_csg = csg_model.run() | ||
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| # 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") | ||
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| 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_2.mean} std dev {csg_result_mat_2.std_dev}' | ||
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| common_geometry_object.export_h5m_file_with_cad_to_dagmc( | ||
| h5m_filename='simpletokamak.h5m', | ||
| material_tags=['1', '2'], | ||
| # the small mesh sizes make a large detailed mesh which is needed to get similar answers | ||
| min_mesh_size=0.01, | ||
| max_mesh_size=0.5 | ||
| ) | ||
| # 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( | ||
| h5m_filename='simpletokamak.h5m', materials=[mat1, mat2]) | ||
| dag_model.tallies = my_tallies | ||
| dag_model.settings = my_settings | ||
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| output_file_from_cad = dag_model.run() | ||
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| # 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") | ||
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| cad_result_mat_1_str = f'CAD tally mean {cad_result_mat_1.mean} std dev {cad_result_mat_1.std_dev}' | ||
| cad_result_mat_2_str = f'CAD tally mean {cad_result_mat_2.mean} std dev {cad_result_mat_2.std_dev}' | ||
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| # printing both tally results | ||
| print(csg_result_mat_1_str) | ||
| print(cad_result_mat_1_str) | ||
| print(csg_result_mat_2_str) | ||
| print(cad_result_mat_2_str) | ||
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| assert math.isclose(cad_result_mat_1.mean, csg_result_mat_1.mean, rel_tol=0.01) | ||
| assert math.isclose(cad_result_mat_2.mean, csg_result_mat_2.mean, rel_tol=0.01) |
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| Original file line number | Diff line number | Diff line change |
|---|---|---|
| @@ -0,0 +1,62 @@ | ||
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| from .utils import BaseCommonGeometryObject | ||
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| class SimpleTokamak(BaseCommonGeometryObject): | ||
| def __init__( | ||
| self, | ||
| radius=500, | ||
| blanket_thicknesses=100, | ||
| center_column_thicknesses=150, | ||
| center_column_extent_beyond_blanket=10, | ||
| ): | ||
| self.radius = radius | ||
| self.blanket_thicknesses = blanket_thicknesses | ||
| self.center_column_thicknesses = center_column_thicknesses | ||
| self.center_column_extent_beyond_blanket = center_column_extent_beyond_blanket | ||
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| def csg_model(self, materials): | ||
| import openmc | ||
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| center_column_height = (self.radius + self.blanket_thicknesses + self.center_column_extent_beyond_blanket)*2 | ||
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| surface_inner_wall = openmc.Sphere(r=self.radius) | ||
| surface_outer_wall = openmc.Sphere(r=self.radius + self.blanket_thicknesses) | ||
| surface_center_cylinder = openmc.ZCylinder(r=self.center_column_thicknesses) | ||
| surface_top_cy = openmc.ZPlane(z0=center_column_height/2, boundary_type='vacuum') | ||
| surface_bot_cy = openmc.ZPlane(z0=-center_column_height/2, boundary_type='vacuum') | ||
| outer_surface = openmc.ZCylinder(r=self.radius + self.blanket_thicknesses, boundary_type='vacuum') | ||
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| region1 = -surface_inner_wall & +surface_center_cylinder # plasma | ||
| region2 = +surface_inner_wall & -surface_outer_wall & +surface_center_cylinder # blanket | ||
| region3 = -surface_top_cy & +surface_bot_cy & -surface_center_cylinder # center column | ||
| region4 = +surface_outer_wall & -surface_top_cy & +surface_bot_cy & +surface_center_cylinder & -outer_surface # outer vessel | ||
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| cell1 = openmc.Cell(region=region1) # plasma | ||
| cell2 = openmc.Cell(region=region2) # blanket | ||
| cell2.fill = materials[0] | ||
| cell3 = openmc.Cell(region=region3) # center column | ||
| cell3.fill = materials[1] | ||
| cell4 = openmc.Cell(region=region4) # outer vessel | ||
|
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| geometry = openmc.Geometry([cell1, cell2, cell3, cell4]) | ||
| materials = openmc.Materials([materials[0], materials[1]]) | ||
| model = openmc.Model(geometry=geometry, materials=materials) | ||
| return model | ||
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| def cadquery_assembly(self): | ||
| import cadquery as cq | ||
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| assembly = cq.Assembly(name="simpletokamak") | ||
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| center_column_height = self.radius + self.blanket_thicknesses + self.center_column_extent_beyond_blanket | ||
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| sphere1 = cq.Workplane().sphere(self.radius) | ||
| sphere2 = cq.Workplane().sphere(self.radius + self.blanket_thicknesses) | ||
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| center_column = cq.Workplane("XY").circle(self.center_column_thicknesses).extrude(center_column_height, both=True) | ||
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| sphere2 = sphere2.cut(sphere1).cut(center_column) | ||
|
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| assembly.add(sphere2) | ||
| assembly.add(center_column) | ||
| return assembly |
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| Original file line number | Diff line number | Diff line change |
|---|---|---|
| @@ -0,0 +1,81 @@ | ||
| from model_benchmark_zoo import SimpleTokamak | ||
| import openmc | ||
| import math | ||
|
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| 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) | ||
|
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| mat2 = openmc.Material(name='2') | ||
| mat2.add_nuclide('Be9', 1) | ||
| mat2.set_density('g/cm3', 1) | ||
|
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| # geometry used in both simulations | ||
| common_geometry_object = SimpleTokamak( | ||
| radius=500, | ||
| blanket_thicknesses=100, | ||
| center_column_thicknesses=50 | ||
| ) | ||
|
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| mat1_filter = openmc.MaterialFilter(mat1) | ||
| tally1 = openmc.Tally(name='mat1_flux_tally') | ||
| tally1.filters = [mat1_filter] | ||
| tally1.scores = ['flux'] | ||
|
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| mat2_filter = openmc.MaterialFilter(mat2) | ||
| tally2 = openmc.Tally(name='mat2_flux_tally') | ||
| tally2.filters = [mat2_filter] | ||
| tally2.scores = ['flux'] | ||
|
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| my_tallies = openmc.Tallies([tally1, tally2]) | ||
|
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| my_settings = openmc.Settings() | ||
| my_settings.batches = 10 | ||
| my_settings.inactive = 0 | ||
| my_settings.particles = 500 | ||
| my_settings.run_mode = 'fixed source' | ||
|
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| # Create a DT ring source | ||
| my_source = openmc.IndependentSource() | ||
| source_r = common_geometry_object.center_column_thicknesses + (common_geometry_object.radius-common_geometry_object.center_column_thicknesses) /2 | ||
| r = openmc.stats.Discrete([source_r], [1]) | ||
| phi = openmc.stats.Uniform(0, 2*math.pi) | ||
| z = openmc.stats.Discrete([0], [1]) | ||
| my_source.space = openmc.stats.CylindricalIndependent(r, phi, z) | ||
| my_source.energy = openmc.stats.Discrete([14e6], [1]) | ||
| my_settings.source = my_source | ||
|
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| # making openmc.Model with CSG geometry | ||
| csg_model = common_geometry_object.csg_model(materials=[mat1, mat2]) | ||
| csg_model.tallies = my_tallies | ||
| csg_model.settings = my_settings | ||
|
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| output_file_from_csg = csg_model.run() | ||
|
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| # 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") | ||
|
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| common_geometry_object.export_h5m_file_with_cad_to_dagmc( | ||
| h5m_filename='simpletokamak.h5m', | ||
| material_tags=['1', '2'], | ||
| max_mesh_size=5, | ||
| min_mesh_size=0.05 | ||
| ) | ||
| # 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(h5m_filename='simpletokamak.h5m', materials=[mat1, mat2]) | ||
| dag_model.tallies = my_tallies | ||
| dag_model.settings = my_settings | ||
|
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| output_file_from_cad = dag_model.run() | ||
|
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| # 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") | ||
|
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| assert math.isclose(cad_result_mat_1.mean, csg_result_mat_1.mean, rel_tol=0.01) | ||
| assert math.isclose(cad_result_mat_2.mean, csg_result_mat_2.mean, rel_tol=0.01) |
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