diff --git a/openmc/examples.py b/openmc/examples.py index d48d26839..a5138377e 100644 --- a/openmc/examples.py +++ b/openmc/examples.py @@ -1,3 +1,5 @@ +from numbers import Integral + import numpy as np import openmc @@ -538,20 +540,20 @@ def pwr_assembly(): return model -def slab_mg(reps=None, as_macro=True): - """Create a one-group, 1D slab model. +def slab_mg(num_regions=1, mat_names=None, mgxslib_name='2g.h5'): + """Create a 1D slab model. Parameters ---------- - reps : list, optional - List of angular representations. Each item corresponds to materials and - dictates the angular representation of the multi-group cross - sections---isotropic ('iso') or angle-dependent ('ang'), and if Legendre - scattering or tabular scattering ('mu') is used. Thus, items can be - 'ang', 'ang_mu', 'iso', or 'iso_mu'. + num_regions : int, optional + Number of regions in the problem, each with a unique MGXS dataset. + Defaults to 1. - as_macro : bool, optional - Whether :class:`openmc.Macroscopic` is used + mat_names : Iterable of str, optional + List of the material names to use; defaults to ['mat_1', 'mat_2',...]. + + mgxslib_name : str, optional + MGXS Library file to use; defaults to '2g.h5'. Returns ------- @@ -559,71 +561,82 @@ def slab_mg(reps=None, as_macro=True): One-group, 1D slab model """ + + openmc.check_type('num_regions', num_regions, Integral) + openmc.check_greater_than('num_regions', num_regions, 0) + if mat_names is not None: + openmc.check_length('mat_names', mat_names, num_regions) + openmc.check_iterable_type('mat_names', mat_names, str) + else: + mat_names = [] + for i in range(num_regions): + mat_names.append('mat_' + str(i + 1)) + + # # Make Materials + materials_file = openmc.Materials() + macros = [] + mats = [] + for i in range(len(mat_names)): + macros.append(openmc.Macroscopic('mat_' + str(i + 1))) + mats.append(openmc.Material(name=mat_names[i])) + mats[-1].set_density('macro', 1.0) + mats[-1].add_macroscopic(macros[-1]) + + materials_file += mats + + materials_file.cross_sections = mgxslib_name + + # # Make Geometry + rad_outer = 929.45 + # Set a cell boundary to exist for every material above (exclude the 0) + rads = np.linspace(0., rad_outer, len(mats) + 1, endpoint=True)[1:] + + # Instantiate Universe + root = openmc.Universe(universe_id=0, name='root universe') + cells = [] + + surfs = [] + surfs.append(openmc.XPlane(x0=0., boundary_type='reflective')) + for r, rad in enumerate(rads): + if r == len(rads) - 1: + surfs.append(openmc.XPlane(x0=rad, boundary_type='vacuum')) + else: + surfs.append(openmc.XPlane(x0=rad)) + + # Instantiate Cells + cells = [] + for c in range(len(surfs) - 1): + cells.append(openmc.Cell()) + cells[-1].region = (+surfs[c] & -surfs[c + 1]) + cells[-1].fill = mats[c] + + # Register Cells with Universe + root.add_cells(cells) + + # Instantiate a Geometry, register the root Universe, and export to XML + geometry_file = openmc.Geometry(root) + + # # Make Settings + # Instantiate a Settings object, set all runtime parameters + settings_file = openmc.Settings() + settings_file.energy_mode = "multi-group" + settings_file.tabular_legendre = {'enable': False} + settings_file.batches = 10 + settings_file.inactive = 5 + settings_file.particles = 1000 + + # Build source distribution + INF = 1000. + bounds = [0., -INF, -INF, rads[0], INF, INF] + uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:]) + settings_file.source = openmc.source.Source(space=uniform_dist) + + settings_file.output = {'summary': False} + model = openmc.model.Model() - - # Define materials needed for 1D/1G slab problem - mat_names = ['uo2', 'clad', 'lwtr'] - mgxs_reps = ['ang', 'ang_mu', 'iso', 'iso_mu'] - - if reps is None: - reps = mgxs_reps - - xs = [] - i = 0 - for mat in mat_names: - for rep in reps: - i += 1 - name = mat + '_' + rep - xs.append(name) - if as_macro: - m = openmc.Material(name=str(i)) - m.set_density('macro', 1.) - m.add_macroscopic(name) - else: - m = openmc.Material(name=str(i)) - m.set_density('atom/b-cm', 1.) - m.add_nuclide(name, 1.0, 'ao') - model.materials.append(m) - - # Define the materials file - model.xs_data = xs - model.materials.cross_sections = "../../1d_mgxs.h5" - - # Define surfaces. - # Assembly/Problem Boundary - left = openmc.XPlane(x0=0.0, boundary_type='reflective') - right = openmc.XPlane(x0=10.0, boundary_type='reflective') - bottom = openmc.YPlane(y0=0.0, boundary_type='reflective') - top = openmc.YPlane(y0=10.0, boundary_type='reflective') - - # for each material add a plane - planes = [openmc.ZPlane(z0=0.0, boundary_type='reflective')] - dz = round(5. / float(len(model.materials)), 4) - for i in range(len(model.materials) - 1): - planes.append(openmc.ZPlane(z0=dz * float(i + 1))) - planes.append(openmc.ZPlane(z0=5.0, boundary_type='reflective')) - - # Define cells for each material - model.geometry.root_universe = openmc.Universe(name='root universe') - xy = +left & -right & +bottom & -top - for i, mat in enumerate(model.materials): - c = openmc.Cell(fill=mat, region=xy & +planes[i] & -planes[i + 1]) - model.geometry.root_universe.add_cell(c) - - model.settings.batches = 10 - model.settings.inactive = 5 - model.settings.particles = 100 - model.settings.source = openmc.Source(space=openmc.stats.Box( - [0.0, 0.0, 0.0], [10.0, 10.0, 5.])) - model.settings.energy_mode = "multi-group" - - plot = openmc.Plot() - plot.filename = 'mat' - plot.origin = (5.0, 5.0, 2.5) - plot.width = (2.5, 2.5) - plot.basis = 'xz' - plot.pixels = (3000, 3000) - plot.color_by = 'material' - model.plots.append(plot) + model.geometry = geometry_file + model.materials = materials_file + model.settings = settings_file + model.xs_data = macros return model diff --git a/tests/1d_mgxs.h5 b/tests/1d_mgxs.h5 deleted file mode 100644 index 0f747345a..000000000 Binary files a/tests/1d_mgxs.h5 and /dev/null differ diff --git a/tests/regression_tests/mg_basic/__init__.py b/tests/regression_tests/mg_basic/__init__.py deleted file mode 100644 index e69de29bb..000000000 diff --git a/tests/regression_tests/mg_basic/inputs_true.dat b/tests/regression_tests/mg_basic/inputs_true.dat deleted file mode 100644 index a0efdbde0..000000000 --- a/tests/regression_tests/mg_basic/inputs_true.dat +++ /dev/null @@ -1,97 +0,0 @@ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ../../1d_mgxs.h5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - eigenvalue - 100 - 10 - 5 - - - 0.0 0.0 0.0 10.0 10.0 5.0 - - - multi-group - diff --git a/tests/regression_tests/mg_basic/results_true.dat b/tests/regression_tests/mg_basic/results_true.dat deleted file mode 100644 index ddb57d00b..000000000 --- a/tests/regression_tests/mg_basic/results_true.dat +++ /dev/null @@ -1,2 +0,0 @@ -k-combined: -1.073147E+00 1.602384E-02 diff --git a/tests/regression_tests/mg_basic/test.py b/tests/regression_tests/mg_basic/test.py deleted file mode 100644 index 3c22e6040..000000000 --- a/tests/regression_tests/mg_basic/test.py +++ /dev/null @@ -1,9 +0,0 @@ -from openmc.examples import slab_mg - -from tests.testing_harness import PyAPITestHarness - - -def test_mg_basic(): - model = slab_mg() - harness = PyAPITestHarness('statepoint.10.h5', model) - harness.main() diff --git a/tests/regression_tests/mg_benchmark/test.py b/tests/regression_tests/mg_benchmark/test.py index 97cef92ad..c29c7ca1f 100644 --- a/tests/regression_tests/mg_benchmark/test.py +++ b/tests/regression_tests/mg_benchmark/test.py @@ -3,6 +3,7 @@ import os import numpy as np import openmc +from openmc.examples import slab_mg from tests.testing_harness import PyAPITestHarness @@ -73,86 +74,6 @@ def create_library(): mg_cross_sections_file.export_to_hdf5('2g.h5') -def create_model(): - create_library() - - # # Make Materials - materials_file = openmc.Materials() - - mat_names = ['base leg', 'base tab', 'base hist', 'base matrix', 'base ang'] - macros = [] - mats = [] - for i in range(len(mat_names)): - macros.append(openmc.Macroscopic('mat_' + str(i + 1))) - mats.append(openmc.Material(name=mat_names[i])) - mats[-1].set_density('macro', 1.0) - mats[-1].add_macroscopic(macros[-1]) - - # Add in the microscopic data - mats.append(openmc.Material(name='micro')) - mats[-1].set_density("sum") - mats[-1].add_nuclide("mat_1", 0.5) - mats[-1].add_nuclide("mat_6", 0.5) - - materials_file += mats - - materials_file.cross_sections = '2g.h5' - - # # Make Geometry - rad_outer = 929.45 - # Set a cell boundary to exist for every material above (exclude the 0) - rads = np.linspace(0., rad_outer, len(mats) + 1, endpoint=True)[1:] - - # Instantiate Universe - root = openmc.Universe(universe_id=0, name='root universe') - cells = [] - - surfs = [] - surfs.append(openmc.XPlane(x0=0., boundary_type='reflective')) - for r, rad in enumerate(rads): - if r == len(rads) - 1: - surfs.append(openmc.XPlane(x0=rad, boundary_type='vacuum')) - else: - surfs.append(openmc.XPlane(x0=rad)) - - # Instantiate Cells - cells = [] - for c in range(len(surfs) - 1): - cells.append(openmc.Cell()) - cells[-1].region = (+surfs[c] & -surfs[c + 1]) - cells[-1].fill = mats[c] - - # Register Cells with Universe - root.add_cells(cells) - - # Instantiate a Geometry, register the root Universe, and export to XML - geometry_file = openmc.Geometry(root) - - # # Make Settings - # Instantiate a Settings object, set all runtime parameters - settings_file = openmc.Settings() - settings_file.energy_mode = "multi-group" - settings_file.tabular_legendre = {'enable': False} - settings_file.batches = 10 - settings_file.inactive = 5 - settings_file.particles = 1000 - - # Build source distribution - INF = 1000. - bounds = [0., -INF, -INF, rads[0], INF, INF] - uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:]) - settings_file.source = openmc.source.Source(space=uniform_dist) - - settings_file.output = {'summary': False} - - model = openmc.model.Model() - model.geometry = geometry_file - model.materials = materials_file - model.settings = settings_file - - return model - - class MGXSTestHarness(PyAPITestHarness): def _cleanup(self): super()._cleanup() @@ -162,6 +83,15 @@ class MGXSTestHarness(PyAPITestHarness): def test_mg_benchmark(): - model = create_model() + create_library() + mat_names = ['base leg', 'base tab', 'base hist', 'base matrix', + 'base ang', 'micro'] + model = slab_mg(num_regions=6, mat_names=mat_names) + # Modify the last material to be a microscopic combination of nuclides + model.materials[-1] = openmc.Material(name='micro', material_id=6) + model.materials[-1].set_density("sum") + model.materials[-1].add_nuclide("mat_1", 0.5) + model.materials[-1].add_nuclide("mat_6", 0.5) + harness = PyAPITestHarness('statepoint.10.h5', model) harness.main() diff --git a/tests/regression_tests/mg_benchmark_delayed/test.py b/tests/regression_tests/mg_benchmark_delayed/test.py index 72bd34e1b..6c527bbe3 100644 --- a/tests/regression_tests/mg_benchmark_delayed/test.py +++ b/tests/regression_tests/mg_benchmark_delayed/test.py @@ -3,6 +3,7 @@ import os import numpy as np import openmc +from openmc.examples import slab_mg from tests.testing_harness import PyAPITestHarness @@ -71,7 +72,8 @@ def create_library(): mat_4 = openmc.XSdata('mat_4', groups) mat_4.order = 1 mat_4.num_delayed_groups = 2 - mat_4.set_prompt_nu_fission(one_m_beta * np.outer(np.multiply(nu, fiss), chi)) + mat_4.set_prompt_nu_fission(one_m_beta * + np.outer(np.multiply(nu, fiss), chi)) delay_nu_fiss = np.zeros((n_dg, groups.num_groups, groups.num_groups)) for dg in range(n_dg): for g in range(groups.num_groups): @@ -87,80 +89,6 @@ def create_library(): mg_cross_sections_file.export_to_hdf5('2g.h5') -def create_model(): - create_library() - - # # Make Materials - materials_file = openmc.Materials() - - mat_names = ['vec beta', 'vec no beta', 'matrix beta', 'matrix no beta'] - macros = [] - mats = [] - for i in range(len(mat_names)): - macros.append(openmc.Macroscopic('mat_' + str(i + 1))) - mats.append(openmc.Material(name=mat_names[i])) - mats[-1].set_density('macro', 1.0) - mats[-1].add_macroscopic(macros[-1]) - - materials_file += mats - - materials_file.cross_sections = '2g.h5' - - # # Make Geometry - rad_outer = 929.45 - # Set a cell boundary to exist for every material above (exclude the 0) - rads = np.linspace(0., rad_outer, len(mats) + 1, endpoint=True)[1:] - - # Instantiate Universe - root = openmc.Universe(universe_id=0, name='root universe') - cells = [] - - surfs = [] - surfs.append(openmc.XPlane(x0=0., boundary_type='reflective')) - for r, rad in enumerate(rads): - if r == len(rads) - 1: - surfs.append(openmc.XPlane(x0=rad, boundary_type='vacuum')) - else: - surfs.append(openmc.XPlane(x0=rad)) - - # Instantiate Cells - cells = [] - for c in range(len(surfs) - 1): - cells.append(openmc.Cell()) - cells[-1].region = (+surfs[c] & -surfs[c + 1]) - cells[-1].fill = mats[c] - - # Register Cells with Universe - root.add_cells(cells) - - # Instantiate a Geometry, register the root Universe, and export to XML - geometry_file = openmc.Geometry(root) - - # # Make Settings - # Instantiate a Settings object, set all runtime parameters - settings_file = openmc.Settings() - settings_file.energy_mode = "multi-group" - settings_file.tabular_legendre = {'enable': False} - settings_file.batches = 10 - settings_file.inactive = 5 - settings_file.particles = 1000 - - # Build source distribution - INF = 1000. - bounds = [0., -INF, -INF, rads[0], INF, INF] - uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:]) - settings_file.source = openmc.source.Source(space=uniform_dist) - - settings_file.output = {'summary': False} - - model = openmc.model.Model() - model.geometry = geometry_file - model.materials = materials_file - model.settings = settings_file - - return model - - class MGXSTestHarness(PyAPITestHarness): def _cleanup(self): super()._cleanup() @@ -170,6 +98,9 @@ class MGXSTestHarness(PyAPITestHarness): def test_mg_benchmark(): - model = create_model() + create_library() + model = slab_mg(num_regions=4, mat_names=['vec beta', 'vec no beta', + 'matrix beta', 'matrix no beta']) + harness = PyAPITestHarness('statepoint.10.h5', model) harness.main() diff --git a/tests/regression_tests/mg_convert/test.py b/tests/regression_tests/mg_convert/test.py index 1ace10c80..4cc6b656a 100755 --- a/tests/regression_tests/mg_convert/test.py +++ b/tests/regression_tests/mg_convert/test.py @@ -17,7 +17,7 @@ def build_mgxs_library(convert): # Instantiate the energy group data groups = openmc.mgxs.EnergyGroups(group_edges=[1e-5, 0.625, 20.0e6]) - # Instantiate the 7-group (C5G7) cross section data + # Instantiate the 2-group (C5G7) cross section data uo2_xsdata = openmc.XSdata('UO2', groups) uo2_xsdata.order = 2 uo2_xsdata.set_total([2., 2.]) diff --git a/tests/regression_tests/mg_legendre/inputs_true.dat b/tests/regression_tests/mg_legendre/inputs_true.dat index 754808095..ad3b434e6 100644 --- a/tests/regression_tests/mg_legendre/inputs_true.dat +++ b/tests/regression_tests/mg_legendre/inputs_true.dat @@ -1,44 +1,31 @@ - - - + - - - - - - - + - ../../1d_mgxs.h5 - + 2g.h5 + - - - - - - - - - + eigenvalue - 100 + 1000 10 5 - 0.0 0.0 0.0 10.0 10.0 5.0 + 0.0 -1000.0 -1000.0 929.45 1000.0 1000.0 + + false + multi-group false diff --git a/tests/regression_tests/mg_legendre/results_true.dat b/tests/regression_tests/mg_legendre/results_true.dat index d0f8c319e..4a9d98237 100644 --- a/tests/regression_tests/mg_legendre/results_true.dat +++ b/tests/regression_tests/mg_legendre/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.110122E+00 2.549637E-02 +9.934975E-01 2.679669E-02 diff --git a/tests/regression_tests/mg_legendre/test.py b/tests/regression_tests/mg_legendre/test.py index 5a57f758e..b5a05c706 100644 --- a/tests/regression_tests/mg_legendre/test.py +++ b/tests/regression_tests/mg_legendre/test.py @@ -1,10 +1,54 @@ +import os + +import numpy as np + +import openmc from openmc.examples import slab_mg from tests.testing_harness import PyAPITestHarness +def create_library(): + # Instantiate the energy group data and file object + groups = openmc.mgxs.EnergyGroups(group_edges=[0.0, 0.625, 20.0e6]) + + mg_cross_sections_file = openmc.MGXSLibrary(groups) + + # Make the base, isotropic data + nu = [2.50, 2.50] + fiss = np.array([0.002817, 0.097]) + capture = [0.008708, 0.02518] + absorption = np.add(capture, fiss) + scatter = np.array( + [[[0.31980, 0.06694], [0.004555, -0.0003972]], + [[0.00000, 0.00000], [0.424100, 0.05439000]]]) + total = [0.33588, 0.54628] + chi = [1., 0.] + + mat_1 = openmc.XSdata('mat_1', groups) + mat_1.order = 1 + mat_1.set_nu_fission(np.multiply(nu, fiss)) + mat_1.set_absorption(absorption) + mat_1.set_scatter_matrix(scatter) + mat_1.set_total(total) + mat_1.set_chi(chi) + mg_cross_sections_file.add_xsdata(mat_1) + + # Write the file + mg_cross_sections_file.export_to_hdf5('2g.h5') + + +class MGXSTestHarness(PyAPITestHarness): + def _cleanup(self): + super()._cleanup() + f = '2g.h5' + if os.path.exists(f): + os.remove(f) + + def test_mg_legendre(): - model = slab_mg(reps=['iso']) + create_library() + model = slab_mg() model.settings.tabular_legendre = {'enable': False} harness = PyAPITestHarness('statepoint.10.h5', model) diff --git a/tests/regression_tests/mg_max_order/inputs_true.dat b/tests/regression_tests/mg_max_order/inputs_true.dat index 023d468d4..2ac83852c 100644 --- a/tests/regression_tests/mg_max_order/inputs_true.dat +++ b/tests/regression_tests/mg_max_order/inputs_true.dat @@ -1,44 +1,34 @@ - - - + - - - - - - - + - ../../1d_mgxs.h5 - + 2g.h5 + - - - - - - - - - + eigenvalue - 100 + 1000 10 5 - 0.0 0.0 0.0 10.0 10.0 5.0 + 0.0 -1000.0 -1000.0 929.45 1000.0 1000.0 + + false + multi-group 1 + + false + diff --git a/tests/regression_tests/mg_max_order/results_true.dat b/tests/regression_tests/mg_max_order/results_true.dat index adfcd44a8..4a9d98237 100644 --- a/tests/regression_tests/mg_max_order/results_true.dat +++ b/tests/regression_tests/mg_max_order/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.074551E+00 1.871525E-02 +9.934975E-01 2.679669E-02 diff --git a/tests/regression_tests/mg_max_order/test.py b/tests/regression_tests/mg_max_order/test.py index 20cc4f805..97d3f57d7 100644 --- a/tests/regression_tests/mg_max_order/test.py +++ b/tests/regression_tests/mg_max_order/test.py @@ -1,10 +1,55 @@ +import os + +import numpy as np + +import openmc from openmc.examples import slab_mg from tests.testing_harness import PyAPITestHarness +def create_library(): + # Instantiate the energy group data and file object + groups = openmc.mgxs.EnergyGroups(group_edges=[0.0, 0.625, 20.0e6]) + + mg_cross_sections_file = openmc.MGXSLibrary(groups) + + # Make the base, isotropic data + nu = [2.50, 2.50] + fiss = np.array([0.002817, 0.097]) + capture = [0.008708, 0.02518] + absorption = np.add(capture, fiss) + scatter = np.array( + [[[0.31980, 0.06694, 0.003], [0.004555, -0.0003972, 0.00002]], + [[0.00000, 0.00000, 0.000], [0.424100, 0.05439000, 0.0025]]]) + total = [0.33588, 0.54628] + chi = [1., 0.] + + mat_1 = openmc.XSdata('mat_1', groups) + mat_1.order = 2 + mat_1.set_nu_fission(np.multiply(nu, fiss)) + mat_1.set_absorption(absorption) + mat_1.set_scatter_matrix(scatter) + mat_1.set_total(total) + mat_1.set_chi(chi) + mg_cross_sections_file.add_xsdata(mat_1) + + # Write the file + mg_cross_sections_file.export_to_hdf5('2g.h5') + + +class MGXSTestHarness(PyAPITestHarness): + def _cleanup(self): + super()._cleanup() + f = '2g.h5' + if os.path.exists(f): + os.remove(f) + + def test_mg_max_order(): - model = slab_mg(reps=['iso']) + create_library() + model = slab_mg() model.settings.max_order = 1 + harness = PyAPITestHarness('statepoint.10.h5', model) harness.main() diff --git a/tests/regression_tests/mg_nuclide/__init__.py b/tests/regression_tests/mg_nuclide/__init__.py deleted file mode 100644 index e69de29bb..000000000 diff --git a/tests/regression_tests/mg_nuclide/inputs_true.dat b/tests/regression_tests/mg_nuclide/inputs_true.dat deleted file mode 100644 index e11b9e3f0..000000000 --- a/tests/regression_tests/mg_nuclide/inputs_true.dat +++ /dev/null @@ -1,97 +0,0 @@ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ../../1d_mgxs.h5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - eigenvalue - 100 - 10 - 5 - - - 0.0 0.0 0.0 10.0 10.0 5.0 - - - multi-group - diff --git a/tests/regression_tests/mg_nuclide/results_true.dat b/tests/regression_tests/mg_nuclide/results_true.dat deleted file mode 100644 index ddb57d00b..000000000 --- a/tests/regression_tests/mg_nuclide/results_true.dat +++ /dev/null @@ -1,2 +0,0 @@ -k-combined: -1.073147E+00 1.602384E-02 diff --git a/tests/regression_tests/mg_nuclide/test.py b/tests/regression_tests/mg_nuclide/test.py deleted file mode 100644 index 44206ef28..000000000 --- a/tests/regression_tests/mg_nuclide/test.py +++ /dev/null @@ -1,9 +0,0 @@ -from openmc.examples import slab_mg - -from tests.testing_harness import PyAPITestHarness - - -def test_mg_nuclide(): - model = slab_mg(as_macro=False) - harness = PyAPITestHarness('statepoint.10.h5', model) - harness.main() diff --git a/tests/regression_tests/mg_survival_biasing/inputs_true.dat b/tests/regression_tests/mg_survival_biasing/inputs_true.dat index 4bc79d48e..5ece3ce9f 100644 --- a/tests/regression_tests/mg_survival_biasing/inputs_true.dat +++ b/tests/regression_tests/mg_survival_biasing/inputs_true.dat @@ -1,98 +1,34 @@ - - - - - - - - - - - - + - - - - - - - - - - - - - - - - + - ../../1d_mgxs.h5 - + 2g.h5 + - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - + eigenvalue - 100 + 1000 10 5 - 0.0 0.0 0.0 10.0 10.0 5.0 + 0.0 -1000.0 -1000.0 929.45 1000.0 1000.0 + + false + multi-group true + + false + diff --git a/tests/regression_tests/mg_survival_biasing/results_true.dat b/tests/regression_tests/mg_survival_biasing/results_true.dat index b20d63288..ebe98679f 100644 --- a/tests/regression_tests/mg_survival_biasing/results_true.dat +++ b/tests/regression_tests/mg_survival_biasing/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.080832E+00 1.336780E-02 +9.979905E-01 6.207495E-03 diff --git a/tests/regression_tests/mg_survival_biasing/test.py b/tests/regression_tests/mg_survival_biasing/test.py index 3c6c77a37..5d75611a9 100644 --- a/tests/regression_tests/mg_survival_biasing/test.py +++ b/tests/regression_tests/mg_survival_biasing/test.py @@ -1,10 +1,55 @@ +import os + +import numpy as np + +import openmc from openmc.examples import slab_mg from tests.testing_harness import PyAPITestHarness +def create_library(): + # Instantiate the energy group data and file object + groups = openmc.mgxs.EnergyGroups(group_edges=[0.0, 0.625, 20.0e6]) + + mg_cross_sections_file = openmc.MGXSLibrary(groups) + + # Make the base, isotropic data + nu = [2.50, 2.50] + fiss = np.array([0.002817, 0.097]) + capture = [0.008708, 0.02518] + absorption = np.add(capture, fiss) + scatter = np.array( + [[[0.31980, 0.06694], [0.004555, -0.0003972]], + [[0.00000, 0.00000], [0.424100, 0.05439000]]]) + total = [0.33588, 0.54628] + chi = [1., 0.] + + mat_1 = openmc.XSdata('mat_1', groups) + mat_1.order = 1 + mat_1.set_nu_fission(np.multiply(nu, fiss)) + mat_1.set_absorption(absorption) + mat_1.set_scatter_matrix(scatter) + mat_1.set_total(total) + mat_1.set_chi(chi) + mg_cross_sections_file.add_xsdata(mat_1) + + # Write the file + mg_cross_sections_file.export_to_hdf5('2g.h5') + + +class MGXSTestHarness(PyAPITestHarness): + def _cleanup(self): + super()._cleanup() + f = '2g.h5' + if os.path.exists(f): + os.remove(f) + + def test_mg_survival_biasing(): + create_library() model = slab_mg() model.settings.survival_biasing = True + harness = PyAPITestHarness('statepoint.10.h5', model) harness.main() diff --git a/tests/regression_tests/mg_tallies/inputs_true.dat b/tests/regression_tests/mg_tallies/inputs_true.dat index 7b5067014..a9b821c56 100644 --- a/tests/regression_tests/mg_tallies/inputs_true.dat +++ b/tests/regression_tests/mg_tallies/inputs_true.dat @@ -1,112 +1,48 @@ - - - - - - - - - - - - + - - - - - - - - - - - - - - - - + - ../../1d_mgxs.h5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - + 2g.h5 + + + eigenvalue - 100 + 1000 10 5 - 0.0 0.0 0.0 10.0 10.0 5.0 + 0.0 -1000.0 -1000.0 929.45 1000.0 1000.0 + + false + multi-group + + false + - 1 1 10 + 10 1 1 0.0 0.0 0.0 - 10 10 5 + 929.45 1000 1000 1 - 1 2 3 4 5 6 7 8 9 10 11 12 + 1 0.0 20000000.0 @@ -115,10 +51,10 @@ 0.0 20000000.0 - 1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0 + 0.0 0.625 20000000.0 - 1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0 + 0.0 0.625 20000000.0 5 @@ -170,60 +106,60 @@ 5 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission analog 5 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission tracklength 6 1 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission scatter nu-scatter analog 6 1 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission collision 6 1 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission tracklength 6 1 2 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 scatter nu-scatter nu-fission 6 3 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission scatter nu-scatter analog 6 3 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission collision 6 3 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 total absorption fission nu-fission tracklength 6 3 4 - uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu + mat_1 scatter nu-scatter nu-fission diff --git a/tests/regression_tests/mg_tallies/results_true.dat b/tests/regression_tests/mg_tallies/results_true.dat index 87470bdf4..78a5883fe 100644 --- a/tests/regression_tests/mg_tallies/results_true.dat +++ b/tests/regression_tests/mg_tallies/results_true.dat @@ -1 +1 @@ -9183f8b191f2e62334f992acd865d29e3f4e3f871a6df498e280fc4e2d91f2d2d20c732fbd75fa88e2e8c576f86e744f7655af6bb9da66e9b28b1009c8742899 \ No newline at end of file +41ea1f6b17c58a8141921af2f1d044eda93f3a9bca9463ee023af2e9865da613ace90fc8a25b42edde128ed827182ea9df0fe09d9b7887282d0ec092692cf717 \ No newline at end of file diff --git a/tests/regression_tests/mg_tallies/test.py b/tests/regression_tests/mg_tallies/test.py index 8952cc4ad..26d53c230 100644 --- a/tests/regression_tests/mg_tallies/test.py +++ b/tests/regression_tests/mg_tallies/test.py @@ -1,23 +1,66 @@ +import os + +import numpy as np + import openmc from openmc.examples import slab_mg from tests.testing_harness import HashedPyAPITestHarness +def create_library(): + # Instantiate the energy group data and file object + groups = openmc.mgxs.EnergyGroups(group_edges=[0.0, 0.625, 20.0e6]) + + mg_cross_sections_file = openmc.MGXSLibrary(groups) + + # Make the base, isotropic data + nu = [2.50, 2.50] + fiss = np.array([0.002817, 0.097]) + capture = [0.008708, 0.02518] + absorption = np.add(capture, fiss) + scatter = np.array( + [[[0.31980, 0.06694], [0.004555, -0.0003972]], + [[0.00000, 0.00000], [0.424100, 0.05439000]]]) + total = [0.33588, 0.54628] + chi = [1., 0.] + + mat_1 = openmc.XSdata('mat_1', groups) + mat_1.order = 1 + mat_1.set_nu_fission(np.multiply(nu, fiss)) + mat_1.set_absorption(absorption) + mat_1.set_scatter_matrix(scatter) + mat_1.set_total(total) + mat_1.set_chi(chi) + mg_cross_sections_file.add_xsdata(mat_1) + + # Write the file + mg_cross_sections_file.export_to_hdf5('2g.h5') + + +class MGXSTestHarness(HashedPyAPITestHarness): + def _cleanup(self): + super()._cleanup() + f = '2g.h5' + if os.path.exists(f): + os.remove(f) + + def test_mg_tallies(): - model = slab_mg(as_macro=False) + create_library() + model = slab_mg() # Instantiate a tally mesh mesh = openmc.Mesh(mesh_id=1) mesh.type = 'regular' - mesh.dimension = [1, 1, 10] + mesh.dimension = [10, 1, 1] mesh.lower_left = [0.0, 0.0, 0.0] - mesh.upper_right = [10, 10, 5] + mesh.upper_right = [929.45, 1000, 1000] # Instantiate some tally filters energy_filter = openmc.EnergyFilter([0.0, 20.0e6]) energyout_filter = openmc.EnergyoutFilter([0.0, 20.0e6]) - energies = [1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6] + energies = [0.0, 0.625, 20.0e6] matching_energy_filter = openmc.EnergyFilter(energies) matching_eout_filter = openmc.EnergyoutFilter(energies) mesh_filter = openmc.MeshFilter(mesh)