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Review improvement from @paulromano

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Jonathan Shimwell 2023-01-28 17:18:35 +00:00 • committed by GitHub
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openmc/deplete/results.py
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@ -396,7 +396,7 @@ class Results(list):
materials.xml will be used. If that element is not present,
nuclides from openmc.config['cross_sections'] will be used.
path : PathLike
Path to file to write. Defaults to 'materials.xml'.
Path to materials XML file to read. Defaults to 'materials.xml'.
Returns
-------