def test_mg_max_order(): create_library() model = slab_mg() model.settings.max_order = 1 harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
def test_mg_survival_biasing(): create_library() model = slab_mg() model.settings.survival_biasing = True harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
def test_mg_basic_delayed(): create_library() model = slab_mg(num_regions=6, mat_names=[ 'vec beta', 'vec no beta', 'matrix beta', 'matrix no beta', 'vec group beta', 'matrix group beta' ]) harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
def test_mg_basic(): 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()
#!/usr/bin/env python import os import sys sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness from openmc.examples import slab_mg if __name__ == '__main__': model = slab_mg() model.settings.survival_biasing = True harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
#!/usr/bin/env python import os import sys sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness from openmc.examples import slab_mg if __name__ == '__main__': model = slab_mg() model.settings.survival_biasing = True harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
#!/usr/bin/env python import os import sys sys.path.insert(0, os.pardir) from testing_harness import HashedPyAPITestHarness import openmc from openmc.examples import slab_mg if __name__ == '__main__': model = slab_mg(as_macro=False) # Instantiate a tally mesh mesh = openmc.Mesh(mesh_id=1) mesh.type = 'regular' mesh.dimension = [1, 1, 10] mesh.lower_left = [0.0, 0.0, 0.0] mesh.upper_right = [10, 10, 5] # 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] matching_energy_filter = openmc.EnergyFilter(energies) matching_eout_filter = openmc.EnergyoutFilter(energies) mesh_filter = openmc.MeshFilter(mesh) mat_filter = openmc.MaterialFilter(model.materials) nuclides = model.xs_data
#!/usr/bin/env python import os import sys sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness from openmc.examples import slab_mg if __name__ == '__main__': model = slab_mg(reps=['iso']) model.settings.tabular_legendre = {'enable': False} harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
#!/usr/bin/env python import os import sys sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness from openmc.examples import slab_mg if __name__ == '__main__': model = slab_mg(reps=['iso']) model.settings.max_order = 1 harness = PyAPITestHarness('statepoint.10.h5', model) harness.main()
def test_mg_tallies(): create_library() model = slab_mg() # Instantiate a tally mesh mesh = openmc.RegularMesh(mesh_id=1) mesh.dimension = [10, 1, 1] mesh.lower_left = [0.0, 0.0, 0.0] 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 = [0.0, 0.625, 20.0e6] matching_energy_filter = openmc.EnergyFilter(energies) matching_eout_filter = openmc.EnergyoutFilter(energies) mesh_filter = openmc.MeshFilter(mesh) mat_filter = openmc.MaterialFilter(model.materials) nuclides = model.xs_data scores_with_nuclides = [ 'total', 'absorption', 'fission', 'nu-fission', 'inverse-velocity', 'prompt-nu-fission', 'delayed-nu-fission', 'kappa-fission', 'events', 'decay-rate' ] scores_without_nuclides = scores_with_nuclides + ['flux'] for do_nuclides, scores in ((False, scores_without_nuclides), (True, scores_with_nuclides)): t = openmc.Tally() t.filters = [mesh_filter] t.estimator = 'analog' t.scores = scores if do_nuclides: t.nuclides = nuclides model.tallies.append(t) t = openmc.Tally() t.filters = [mesh_filter] t.estimator = 'tracklength' t.scores = scores if do_nuclides: t.nuclides = nuclides model.tallies.append(t) # Impose energy bins that dont match the MG structure and those # that do for match_energy_bins in [False, True]: if match_energy_bins: e_filter = matching_energy_filter eout_filter = matching_eout_filter else: e_filter = energy_filter eout_filter = energyout_filter t = openmc.Tally() t.filters = [mat_filter, e_filter] t.estimator = 'analog' t.scores = scores + ['scatter', 'nu-scatter'] if do_nuclides: t.nuclides = nuclides model.tallies.append(t) t = openmc.Tally() t.filters = [mat_filter, e_filter] t.estimator = 'collision' t.scores = scores if do_nuclides: t.nuclides = nuclides model.tallies.append(t) t = openmc.Tally() t.filters = [mat_filter, e_filter] t.estimator = 'tracklength' t.scores = scores if do_nuclides: t.nuclides = nuclides model.tallies.append(t) t = openmc.Tally() t.filters = [mat_filter, e_filter, eout_filter] t.scores = ['scatter', 'nu-scatter', 'nu-fission'] if do_nuclides: t.nuclides = nuclides model.tallies.append(t) harness = MGXSTestHarness('statepoint.10.h5', model) harness.main()