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added to altered functions docstring

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Jonathan Shimwell 2020-10-08 17:33:05 +01:00
parent e71e09884d
commit 336b09b358
1 changed files with 3 additions and 2 deletions
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openmc/plotter.py
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@ -309,8 +309,9 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None,
Nuclide object to source data from
types : Iterable of str or Integral
The type of cross sections to calculate; values can either be those
in openmc.PLOT_TYPES or integers which correspond to reaction
channel (MT) numbers.
in openmc.PLOT_TYPES or keys from openmc.data.REACTION_NUMBER which
correspond to a reaction description e.g '(n,2n)' or integers which
correspond to reaction channel (MT) numbers.
temperature : float, optional
Temperature in Kelvin to plot. If not specified, a default
temperature of 294K will be plotted. Note that the nearest