diff --git a/examples/custom_source/build_xml.py b/examples/custom_source/build_xml.py index e9a9a06568..6db136216d 100644 --- a/examples/custom_source/build_xml.py +++ b/examples/custom_source/build_xml.py @@ -18,7 +18,7 @@ settings = openmc.Settings() settings.run_mode = 'fixed source' settings.batches = 10 settings.particles = 1000 -source = openmc.IndependentSource() +source = openmc.CompiledSource() source.library = 'build/libsource.so' settings.source = source settings.export_to_xml() diff --git a/examples/lattice/hexagonal/build_xml.py b/examples/lattice/hexagonal/build_xml.py index c0aa815b41..96ff3f34a1 100644 --- a/examples/lattice/hexagonal/build_xml.py +++ b/examples/lattice/hexagonal/build_xml.py @@ -115,7 +115,7 @@ settings_file.particles = particles # Create an initial uniform spatial source distribution over fissionable zones bounds = [-1, -1, -1, 1, 1, 1] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True) -settings_file.source = openmc.source.Source(space=uniform_dist) +settings_file.source = openmc.IndependentSource(space=uniform_dist) settings_file.keff_trigger = {'type' : 'std_dev', 'threshold' : 5E-4} settings_file.trigger_active = True diff --git a/examples/lattice/nested/build_xml.py b/examples/lattice/nested/build_xml.py index 06641f5ac5..407a53a232 100644 --- a/examples/lattice/nested/build_xml.py +++ b/examples/lattice/nested/build_xml.py @@ -125,7 +125,7 @@ settings_file.particles = particles # Create an initial uniform spatial source distribution over fissionable zones bounds = [-1, -1, -1, 1, 1, 1] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True) -settings_file.source = openmc.source.Source(space=uniform_dist) +settings_file.source = openmc.IndependentSource(space=uniform_dist) settings_file.export_to_xml() diff --git a/examples/lattice/simple/build_xml.py b/examples/lattice/simple/build_xml.py index 17544b87f5..0da8d8cf08 100644 --- a/examples/lattice/simple/build_xml.py +++ b/examples/lattice/simple/build_xml.py @@ -116,7 +116,7 @@ settings_file.particles = particles # Create an initial uniform spatial source distribution over fissionable zones bounds = [-1, -1, -1, 1, 1, 1] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True) -settings_file.source = openmc.source.Source(space=uniform_dist) +settings_file.source = openmc.IndependentSource(space=uniform_dist) settings_file.trigger_active = True settings_file.trigger_max_batches = 100 diff --git a/examples/parameterized_custom_source/build_xml.py b/examples/parameterized_custom_source/build_xml.py index 3c67e244dc..23d9930c0f 100644 --- a/examples/parameterized_custom_source/build_xml.py +++ b/examples/parameterized_custom_source/build_xml.py @@ -18,7 +18,7 @@ settings = openmc.Settings() settings.run_mode = 'fixed source' settings.batches = 10 settings.particles = 1000 -source = openmc.IndependentSource() +source = openmc.CompiledSource() source.library = 'build/libparameterized_source.so' source.parameters = 'radius=3.0, energy=14.08e6' settings.source = source diff --git a/examples/pincell/build_xml.py b/examples/pincell/build_xml.py index c5d614ea90..cd8923fbea 100644 --- a/examples/pincell/build_xml.py +++ b/examples/pincell/build_xml.py @@ -68,7 +68,7 @@ settings.particles = 1000 lower_left = (-pitch/2, -pitch/2, -1) upper_right = (pitch/2, pitch/2, 1) uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True) -settings.source = openmc.source.Source(space=uniform_dist) +settings.source = openmc.IndependentSource(space=uniform_dist) # For source convergence checks, add a mesh that can be used to calculate the # Shannon entropy diff --git a/examples/pincell_depletion/restart_depletion.py b/examples/pincell_depletion/restart_depletion.py index 6bb715f3b5..ac065d3402 100644 --- a/examples/pincell_depletion/restart_depletion.py +++ b/examples/pincell_depletion/restart_depletion.py @@ -27,7 +27,7 @@ settings.particles = 10000 # Create an initial uniform spatial source distribution over fissionable zones bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True) -settings.source = openmc.source.Source(space=uniform_dist) +settings.source = openmc.IndependentSource(space=uniform_dist) entropy_mesh = openmc.RegularMesh() entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50] diff --git a/examples/pincell_depletion/run_depletion.py b/examples/pincell_depletion/run_depletion.py index 6a6c25f59b..493e311783 100644 --- a/examples/pincell_depletion/run_depletion.py +++ b/examples/pincell_depletion/run_depletion.py @@ -72,7 +72,7 @@ settings.particles = 1000 # Create an initial uniform spatial source distribution over fissionable zones bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True) -settings.source = openmc.source.Source(space=uniform_dist) +settings.source = openmc.IndependentSource(space=uniform_dist) entropy_mesh = openmc.RegularMesh() entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50] diff --git a/examples/pincell_multigroup/build_xml.py b/examples/pincell_multigroup/build_xml.py index 1f34683919..48671698d0 100644 --- a/examples/pincell_multigroup/build_xml.py +++ b/examples/pincell_multigroup/build_xml.py @@ -114,7 +114,7 @@ settings.particles = 1000 lower_left = (-pitch/2, -pitch/2, -1) upper_right = (pitch/2, pitch/2, 1) uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True) -settings.source = openmc.source.Source(space=uniform_dist) +settings.source = openmc.IndependentSource(space=uniform_dist) settings.export_to_xml() ############################################################################### diff --git a/tests/unit_tests/weightwindows/test_ww_gen.py b/tests/unit_tests/weightwindows/test_ww_gen.py index 74bbcfadae..a5f65ff617 100644 --- a/tests/unit_tests/weightwindows/test_ww_gen.py +++ b/tests/unit_tests/weightwindows/test_ww_gen.py @@ -62,7 +62,7 @@ def model(): # 10 keV neutron point source at the origin space = openmc.stats.Point() energy = openmc.stats.Discrete(x=[1e4], p=[1.0]) - settings.source = openmc.Source(space=space, energy=energy) + settings.source = openmc.IndependentSource(space=space, energy=energy) return openmc.Model(geometry=geometry, settings=settings)