format

examples/point_source_example.py

@@ -38,7 +38,7 @@
 
 plot = plot_source_energy(
     this=settings,
-    n_samples=1000000, # increase this value for a smoother plot
+    n_samples=1000000,  # increase this value for a smoother plot
     energy_bins=np.linspace(0, 16e6, 1000),
     yaxis_type="log",
 )

examples/tokamak_source_example.py

@@ -52,9 +52,6 @@
 
 from openmc_source_plotter import plot_source_direction
 
-plot = plot_source_direction(
-    this=settings,
-    n_samples=200
-)
+plot = plot_source_direction(this=settings, n_samples=200)
 
 plot.show()

src/openmc_plasma_source/fuel_types.py

@@ -93,18 +93,18 @@ def neutron_energy_std_dev(ion_temperature: float, reaction: str) -> float:
     return std_dev
 
 
-
 def get_reactions_from_fuel(fuel):
     if ["D", "T"] == sorted(set(fuel.keys())):
-        return ['DT', 'DD', 'TT']
+        return ["DT", "DD", "TT"]
     elif ["D"] == sorted(set(fuel.keys())):
-        return ['DD']
+        return ["DD"]
     elif ["T"] == sorted(set(fuel.keys())):
-        return ['TT']
+        return ["TT"]
     else:
         msg = 'reactions of fuel {fuel} could not be found. Supported fuel keys are "T" and "D"'
         raise ValueError(msg)
 
+
 def get_neutron_energy_distribution(
     ion_temperature: float,
     fuel: dict,
@@ -160,16 +160,16 @@ def get_neutron_energy_distribution(
 
     reactions = get_reactions_from_fuel(fuel)
 
-    if reactions == ['TT']:
+    if reactions == ["TT"]:
         strength_TT = 1.0
         dNdE_TT = strength_TT * nst.dNdE_TT(E_pspec, ion_temperature)
         tt_source = openmc.stats.Tabular(E_pspec * 1e6, dNdE_TT)
-        return {'TT': tt_source}, {'TT': strength_TT}
+        return {"TT": tt_source}, {"TT": strength_TT}
 
     elif reactions == ["DD"]:
         strength_DD = 1.0
         dd_source = openmc.stats.Normal(mean_value=DDmean, std_dev=DD_std_dev)
-        return {'DD': dd_source}, {'DD' :strength_DD}
+        return {"DD": dd_source}, {"DD": strength_DD}
 
     # DT, DD and TT reaction
     else:
@@ -186,9 +186,9 @@ def get_neutron_energy_distribution(
         dNdE_TT = strength_TT * nst.dNdE_TT(E_pspec, ion_temperature)
 
         # removing any zeros from the end of the array
-        dNdE_TT = np.trim_zeros(dNdE_TT, 'b')
+        dNdE_TT = np.trim_zeros(dNdE_TT, "b")
         # making array lengths match
-        E_pspec = E_pspec[:len(dNdE_TT)]
+        E_pspec = E_pspec[: len(dNdE_TT)]
 
         tt_source = openmc.stats.Tabular(E_pspec, dNdE_TT)
 
@@ -202,7 +202,7 @@ def get_neutron_energy_distribution(
 
         # todo look into combining distributions openmc.data.combine_distributions()
         return {
-            'TT': [tt_source, strength_TT / total_strength],
-            'DD': [dd_source, strength_DD / total_strength],
-            'DT': [dt_source, strength_DT / total_strength],
+            "TT": [tt_source, strength_TT / total_strength],
+            "DD": [dd_source, strength_DD / total_strength],
+            "DT": [dt_source, strength_DT / total_strength],
         }

src/openmc_plasma_source/tokamak_source.py

@@ -7,6 +7,7 @@
 from .fuel_types import get_neutron_energy_distribution, get_reactions_from_fuel
 from NeSST.spectral_model import reac_DD, reac_TT, reac_DT
 
+
 def tokamak_source(
     major_radius: float,
     minor_radius: float,
@@ -132,18 +133,18 @@ def tokamak_source(
 
     fuel_densities = {}
     for key, value in fuel.items():
-        fuel_densities[key] = densities*value
+        fuel_densities[key] = densities * value
 
     # compute temperatures
     temperatures = tokamak_ion_temperature(
         r=a,
         mode=mode,
         pedestal_radius=pedestal_radius,
-        ion_temperature_pedestal=ion_temperature_pedestal/1e3,
-        ion_temperature_centre=ion_temperature_centre/1e3,
+        ion_temperature_pedestal=ion_temperature_pedestal / 1e3,
+        ion_temperature_centre=ion_temperature_centre / 1e3,
         ion_temperature_beta=ion_temperature_beta,
         ion_temperature_peaking_factor=ion_temperature_peaking_factor,
-        ion_temperature_separatrix=ion_temperature_separatrix/1e3,
+        ion_temperature_separatrix=ion_temperature_separatrix / 1e3,
         major_radius=major_radius,
     )
 
@@ -159,16 +160,20 @@ def tokamak_source(
     )
 
     reactions = get_reactions_from_fuel(fuel)
-    
-    neutron_source_density={}
+
+    neutron_source_density = {}
     total_source_density = 0
     for reaction in reactions:
-        neutron_source_density[reaction] = tokamak_neutron_source_density(fuel_densities, temperatures, reaction)
+        neutron_source_density[reaction] = tokamak_neutron_source_density(
+            fuel_densities, temperatures, reaction
+        )
         total_source_density += sum(neutron_source_density[reaction])
-    
+
     all_sources = []
     for reaction in reactions:
-        neutron_source_density[reaction] = neutron_source_density[reaction]/total_source_density
+        neutron_source_density[reaction] = (
+            neutron_source_density[reaction] / total_source_density
+        )
 
         sources = tokamak_make_openmc_sources(
             strengths=neutron_source_density,
@@ -353,9 +358,12 @@ def tokamak_make_openmc_sources(
         )
 
         # now we have potentially 3 distributions (DT, DD, TT)
-        for reaction, (energy_distribution, dist_strength) in energy_distributions_and_dist_strengths.items():
+        for reaction, (
+            energy_distribution,
+            dist_strength,
+        ) in energy_distributions_and_dist_strengths.items():
 
-            if dist_strength * strengths[reaction][i] > 0.:
+            if dist_strength * strengths[reaction][i] > 0.0:
                 my_source = openmc.IndependentSource()
 
                 # create a ring source
@@ -387,19 +395,21 @@ def tokamak_neutron_source_density(ion_density, ion_temperature, reaction):
         float, ndarray: Neutron source density (neutron/s/m3)
     """
 
-    ion_density = np.asarray(ion_density[reaction[0]]) * np.asarray(ion_density[reaction[1]])
+    ion_density = np.asarray(ion_density[reaction[0]]) * np.asarray(
+        ion_density[reaction[1]]
+    )
     ion_temperature = np.asarray(ion_temperature)
 
-    if reaction == ['DD']:
+    if reaction == ["DD"]:
         return ion_density * reac_DD(ion_temperature)
-    elif reaction == ['TT']:
+    elif reaction == ["TT"]:
         return ion_density * reac_TT(ion_temperature)
     # ['DT', 'DD', 'TT']
     else:
-        return ion_density * reac_DT(ion_temperature) # could use _DT_xs instead
+        return ion_density * reac_DT(ion_temperature)  # could use _DT_xs instead
 
 
-#TODO consider replace with NeSST or getting DD version as well
+# TODO consider replace with NeSST or getting DD version as well
 def _DT_xs(ion_temperature):
     """Sadler–Van Belle formula
     Ref : https://doi.org/10.1016/j.fusengdes.2012.02.025
@@ -408,7 +418,7 @@ def _DT_xs(ion_temperature):
     Returns:
         float, ndarray: the DT cross section at the given temperature
     """
-    ion_temperature_kev = np.asarray(ion_temperature/1e3)
+    ion_temperature_kev = np.asarray(ion_temperature / 1e3)
     c = [
         2.5663271e-18,
         19.983026,