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OpenMC-mgxs-plot #1135

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MaryHoss opened this issue Jun 12, 2024 · 1 comment
Closed

OpenMC-mgxs-plot #1135

MaryHoss opened this issue Jun 12, 2024 · 1 comment

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@MaryHoss
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hi everyone,

I have created a mgxs in OpenMC13-3 and want to Plot the fission Cross section for U235, and get this error:

fig = openmc.plot_xs('U235', ['fission'])

File "/dss/dsshome1/0C/ge25kij2/.local/lib/python3.8/site-packages/openmc/plotter.py", line 169, in plot_xs
for this, types in reactions.items():
AttributeError: 'str' object has no attribute 'items'

can anyone help me sollte this error?

thank you
Mary

@tom-doerr
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From the documentation

reactions ([dict](https://docs.python.org/3/library/stdtypes.html#dict)) – keys can be either a nuclide or element in string form or an openmc.Material object. Values are the type of cross sections to include in the plot.

You are passing a string, 'U235, which is the wrong type.

Also I don't think this is the right GitHub repo you opened the issue in.

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