Merge branch 'update_package' of github.com:fusion-energy/openmc-plas…

…ma-source into update_package
fusion-energy · Jan 17, 2024 · 780e191 · 780e191
2 parents 37bdd58 + 1731457
commit 780e191
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Showing 3 changed files with 7 additions and 17 deletions.
diff --git a/examples/point_source_example.py b/examples/point_source_example.py
@@ -6,16 +6,12 @@
 openmc.config["cross_sections"] = Path(__file__).parent.resolve() / "cross_sections.xml"
 
 # minimal geometry
-sphere_surface = openmc.Sphere(r=1000.0, boundary_type='vacuum')
+sphere_surface = openmc.Sphere(r=1000.0, boundary_type="vacuum")
 cell = openmc.Cell(region=-sphere_surface)
 geometry = openmc.Geometry([cell])
 
 # define the source
-my_source = FusionPointSource(
-    coordinate=(0, 0, 0),
-    temperature=20000.0,
-    fuel="DT"
-)
+my_source = FusionPointSource(coordinate=(0, 0, 0), temperature=20000.0, fuel="DT")
 
 # Tell OpenMC we're going to use our custom source
 settings = openmc.Settings()
@@ -25,8 +21,6 @@
 settings.source = my_source
 
 
-model = openmc.model.Model(
-    materials=None, geometry=geometry, settings=settings
-)
+model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
 model.run()
diff --git a/examples/ring_source_example.py b/examples/ring_source_example.py
@@ -7,7 +7,7 @@
 openmc.config["cross_sections"] = Path(__file__).parent.resolve() / "cross_sections.xml"
 
 # minimal geometry
-sphere_surface = openmc.Sphere(r=1000.0, boundary_type='vacuum')
+sphere_surface = openmc.Sphere(r=1000.0, boundary_type="vacuum")
 cell = openmc.Cell(region=-sphere_surface)
 geometry = openmc.Geometry([cell])
 
@@ -25,8 +25,6 @@
 # tell OpenMC we're going to use our custom source
 settings.source = my_source
 
-model = openmc.model.Model(
-    materials=None, geometry=geometry, settings=settings
-)
+model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
 model.run()
diff --git a/examples/tokamak_source_example.py b/examples/tokamak_source_example.py
@@ -7,7 +7,7 @@
 
 
 # minimal geometry
-sphere_surface = openmc.Sphere(r=1000.0, boundary_type='vacuum')
+sphere_surface = openmc.Sphere(r=1000.0, boundary_type="vacuum")
 cell = openmc.Cell(region=-sphere_surface)
 geometry = openmc.Geometry([cell])
 
@@ -39,8 +39,6 @@
 settings.source = my_plasma.sources
 
 
-model = openmc.model.Model(
-    materials=None, geometry=geometry, settings=settings
-)
+model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
 model.run()