[skip ci] ring source example working

examples/ring_source_example.py

@@ -3,7 +3,7 @@
 
 import openmc
 
-from openmc_plasma_source import FusionRingSource
+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
 openmc.config["cross_sections"] = Path(__file__).parent.resolve() / "cross_sections.xml"
@@ -14,7 +14,7 @@
 geometry = openmc.Geometry([cell])
 
 # define the source
-my_source = FusionRingSource(
+my_source = fusion_ring_source(
     radius=700,
     angles=(0.0, 2 * math.pi),  # 360deg source
     temperature=20000.0,

src/openmc_plasma_source/point_source.py

@@ -51,7 +51,7 @@ def fusion_point_source(
 
     # else:
     for energy_distribution, strength in zip(energy_distributions, strengths):
-        source = openmc.Source()
+        source = openmc.IndependentSource()
         source.energy = energy_distribution
         source.space = openmc.stats.Point(coordinate)
         source.angle = openmc.stats.Isotropic()

src/openmc_plasma_source/ring_source.py

@@ -53,18 +53,28 @@ def fusion_ring_source(
     else:
         raise ValueError("Temperature must be a float strictly greater than 0.")
 
-    source = openmc.IndependentSource()
-
-    # performed after the super init as these are Source attributes
-    source.space = openmc.stats.CylindricalIndependent(
-        r=openmc.stats.Discrete([radius], [1]),
-        phi=openmc.stats.Uniform(a=angles[0], b=angles[1]),
-        z=openmc.stats.Discrete([z_placement], [1]),
-        origin=(0.0, 0.0, 0.0),
-    )
-    source.angle = openmc.stats.Isotropic()
-    source.energy = get_neutron_energy_distribution(
+
+    sources = []
+
+    energy_distributions, strengths = get_neutron_energy_distribution(
         ion_temperature=temperature, fuel=fuel
     )
 
-    return source
+    for energy_distribution, strength in zip(energy_distributions, strengths):
+
+        source = openmc.IndependentSource()
+
+        source.space = openmc.stats.CylindricalIndependent(
+            r=openmc.stats.Discrete([radius], [1]),
+            phi=openmc.stats.Uniform(a=angles[0], b=angles[1]),
+            z=openmc.stats.Discrete([z_placement], [1]),
+            origin=(0.0, 0.0, 0.0),
+        )
+
+        source.energy = energy_distribution
+        source.angle = openmc.stats.Isotropic()
+        source.strength = strength
+        sources.append(source)
+
+    return sources
+