From 6351b49ea2acf13f90914ef756c6fbf89a296d0a Mon Sep 17 00:00:00 2001
From: yardasol <yardasol@grinnell.edu>
Date: Thu, 28 Jul 2022 16:06:19 -0500
Subject: [PATCH] add reference to add_elements_or_nuclides in the docstring
 for Material

---
 openmc/material.py | 4 +++-
 1 file changed, 3 insertions(+), 1 deletion(-)

diff --git a/openmc/material.py b/openmc/material.py
index 8fee0585c9..14bec12f33 100644
--- a/openmc/material.py
+++ b/openmc/material.py
@@ -34,7 +34,9 @@ class Material(IDManagerMixin):
     To create a material, one should create an instance of this class, add
     nuclides or elements with :meth:`Material.add_nuclide` or
     :meth:`Material.add_element`, respectively, and set the total material
-    density with :meth:`Material.set_density()`. The material can then be
+    density with :meth:`Material.set_density()`. Alternatively, you can
+    use :meth:`Material.add_elements_or_nuclides()` to pass a dictionary
+    containing all the component information. The material can then be
     assigned to a cell using the :attr:`Cell.fill` attribute.
 
     Parameters