From 336b09b358d23d3654a55aa2e1fc7895f70fd4a3 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Thu, 8 Oct 2020 17:33:05 +0100 Subject: [PATCH] added to altered functions docstring --- openmc/plotter.py | 5 +++-- 1 file changed, 3 insertions(+), 2 deletions(-) diff --git a/openmc/plotter.py b/openmc/plotter.py index 28dfcdf885..0994094684 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -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