source plotter does not support stats.univariate.mixture

[rlbarker]

I’ve been using openmc_source_plotter.plot_gamma_emission and found a small bug. It seems that if material.get_decay_photon_energy() (line 50) returns an openmc.stats.univariate.mixture object then the function fails because openmc.stats.univariate.mixture does not have a .p attribute. However, if it returns am openmc.stats.univariate.discrete object, the plotter works fine (as the example does).
I have attached a minimum working example of this code which returns the error:

plt = plot_gamma_emission(material=my_material, label_top=3)
  File "/home/rbarker/miniforge3/envs/openmc_dev/lib/python3.9/site-packages/openmc_source_plotter/material.py", line 51, in plot_gamma_emission
    for p in energy_dis.p:
AttributeError: 'Mixture' object has no attribute 'p'

I have also attached the materials.xml file needed to run this code.

Minimum working example:

import openmc
from openmc_source_plotter import plot_gamma_emission

# This example is modified from https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_gamma_spec_plot.py

# this path will need changing to point to your chain file
openmc.config["chain_file"] = "/home/rbarker/chain.xml"

my_materials = openmc.Materials.from_xml()
my_material = my_materials.pop()

print(my_material.get_decay_photon_energy(clip_tolerance=0.0))

# adds labels to the most active 3 gamma energies
plt = plot_gamma_emission(material=my_material, label_top=3)
plt.xscale("log")
plt.savefig("gamma_spec.png")

materials.xml needed to run this file:

<materials>
<material id="26" volume="0.5078834276747504">
<density units="g/cm3" value="7.3100000000000005"/>
<nuclide ao="9.870374962755434e-116" name="Ag116"/>
<nuclide ao="2.687060094666136e-137" name="Ag117"/>
<nuclide ao="6.186243801149529e-159" name="Ag118"/>
<nuclide ao="0.001641354995525772" name="In113"/>
<nuclide ao="1.3848004856324852e-23" name="In114"/>
<nuclide ao="2.021398689349616e-23" name="In114_m1"/>
<nuclide ao="0.03669910273691459" name="In115"/>
<nuclide ao="7.61819302603757e-43" name="In115_m1"/>
<nuclide ao="5.027376610212269e-22" name="In116"/>
<nuclide ao="3.0847422082568705e-52" name="In117"/>
<nuclide ao="6.3004012242905105e-52" name="In117_m1"/>
</material>
</materials>