From 83a124c49240725494a2f4795aa1e56954c46bf3 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Wed, 22 Mar 2023 13:11:33 +0000 Subject: [PATCH] [skip ci] review improvments to docstring from @paulromano Co-authored-by: Paul Romano --- openmc/plotter.py | 12 ++++++------ 1 file changed, 6 insertions(+), 6 deletions(-) diff --git a/openmc/plotter.py b/openmc/plotter.py index 2bdcfe3519..c66088cfdb 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -63,8 +63,8 @@ def plot_xs(this, types, divisor_types=None, temperature=294., axis=None, Parameters ---------- - this : {str, openmc.Material} - Object to source data from. Nuclides and Elements can be input as a str + this : str or openmc.Material + Object to source data from. Nuclides and elements can be input as a str types : Iterable of values of PLOT_TYPES The type of cross sections to include in the plot. divisor_types : Iterable of values of PLOT_TYPES, optional @@ -217,8 +217,8 @@ def calculate_cexs(this, types, temperature=294., sab_name=None, Parameters ---------- - this : {str, openmc.Material} - Object to source data from. Nuclides and Elements should be input as a + this : str or openmc.Material + Object to source data from. Nuclides and elements should be input as a str types : Iterable of values of PLOT_TYPES The type of cross sections to calculate @@ -603,8 +603,8 @@ def calculate_mgxs(this, types, orders=None, temperature=294., Parameters ---------- - this : {str, openmc.Material} - Object to source data from. Nuclides and Elements can be input as a str + this : str or openmc.Material + Object to source data from. Nuclides and elements can be input as a str types : Iterable of values of PLOT_TYPES_MGXS The type of cross sections to calculate orders : Iterable of Integral, optional