commented out plotly part of examples

.github/workflows/ci.yml

@@ -31,3 +31,6 @@ jobs:
           python examples/point_source_example.py
           python examples/ring_source_example.py
           python examples/tokamak_source_example.py
+          python examples/plot_tokamak_ion_temperature.py
+          python examples/plot_tokamak_neutron_source_density.py
+          python examples/plot_tokamak_neutron_source_strengths.py

examples/point_source_example.py

@@ -2,8 +2,6 @@
 import numpy as np
 
 import openmc
-from openmc_source_plotter import plot_source_energy
-
 from openmc_plasma_source import fusion_point_source
 
 # just making use of a local cross section xml file, replace with your own cross sections or comment out
@@ -28,11 +26,20 @@
 settings.particles = 1000
 settings.source = my_source
 
+model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
-plot = plot_source_energy(
-    this=settings,
-    n_samples=100000,
-    energy_bins=np.linspace(0, 16e6, 1000),
-    yaxis_type="log",
-)
-plot.show()
+model.run()
+
+
+# optionally if you would like to plot the energy of particles then another package can be used
+# https://github.com/fusion-energy/openmc_source_plotter
+
+# from openmc_source_plotter import plot_source_energy
+
+# plot = plot_source_energy(
+#     this=settings,
+#     n_samples=1000000, # increase this value for a smoother plot
+#     energy_bins=np.linspace(0, 16e6, 1000),
+#     yaxis_type="log",
+# )
+# plot.show()

examples/ring_source_example.py

@@ -2,7 +2,6 @@
 from pathlib import Path
 
 import openmc
-
 from openmc_plasma_source import fusion_ring_source
 
 # just making use of a local cross section xml file, replace with your own cross sections or comment out
@@ -31,3 +30,16 @@
 model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
 model.run()
+
+
+# optionally if you would like to plot the location of particles then another package can be used
+# https://github.com/fusion-energy/openmc_source_plotter
+
+# from openmc_source_plotter import plot_source_position
+
+# plot = plot_source_position(
+#     this=settings,
+#     n_samples = 2000,
+# )
+
+# plot.show()

examples/tokamak_source_example.py

@@ -9,7 +9,7 @@
 
 
 # minimal geometry
-sphere_surface = openmc.Sphere(r=1000.0, boundary_type="vacuum")
+sphere_surface = openmc.Sphere(r=100000.0, boundary_type="vacuum")
 cell = openmc.Cell(region=-sphere_surface)
 geometry = openmc.Geometry([cell])
 
@@ -24,9 +24,9 @@
     ion_temperature_peaking_factor=8.06,
     ion_temperature_pedestal=6.09,
     ion_temperature_separatrix=0.1,
-    major_radius=9.06,
-    minor_radius=2.92258,
-    pedestal_radius=0.8 * 2.92258,
+    major_radius=906,
+    minor_radius=292.258,
+    pedestal_radius=0.8 * 292.258,
     mode="H",
     shafranov_factor=0.44789,
     triangularity=0.270,
@@ -45,3 +45,16 @@
 model = openmc.model.Model(materials=None, geometry=geometry, settings=settings)
 
 model.run()
+
+
+# optionally if you would like to plot the direction of particles then another package can be used
+# https://github.com/fusion-energy/openmc_source_plotter
+
+# from openmc_source_plotter import plot_source_direction
+
+# plot = plot_source_direction(
+#     this=settings,
+#     n_samples=200
+# )
+
+# plot.show()