diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb
index 5b3bae495..eaae92f7c 100644
--- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb
+++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb
@@ -519,9 +519,9 @@
    "cell_type": "markdown",
    "metadata": {},
    "source": [
-    "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material\" \"cell\", \"universe\", and \"mesh\" domain types. In this simple example, we wish to compute multi-group cross sections only for each material andtherefore will use a \"material\" domain type.\n",
+    "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material\" \"cell\", \"universe\", and \"mesh\" domain types. In this simple example, we wish to compute multi-group cross sections only for each material and therefore will use a \"material\" domain type.\n",
     "\n",
-    "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell, universe, or mesh cell) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property."
+    "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell, universe, or mesh) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property."
    ]
   },
   {
diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py
index 50d568a2d..84571ce23 100644
--- a/openmc/mgxs/library.py
+++ b/openmc/mgxs/library.py
@@ -56,8 +56,7 @@ class Library(object):
         The types of cross sections in the library (e.g., ['total', 'scatter'])
     domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
         Domain type for spatial homogenization
-    domains : Iterable of openmc.Material, openmc.Cell, openmc.Universe or
-        openmc.Mesh
+    domains : Iterable of openmc.Material, openmc.Cell, openmc.Universe or openmc.Mesh
         The spatial domain(s) for which MGXS in the Library are computed
     correction : {'P0', None}
         Apply the P0 correction to scattering matrices if set to 'P0'
diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py
index f19b50e18..e1c2e6221 100644
--- a/openmc/mgxs/mgxs.py
+++ b/openmc/mgxs/mgxs.py
@@ -439,8 +439,7 @@ class MGXS(object):
         ----------
         mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', 'chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission'}
             The type of multi-group cross section object to return
-        domain : openmc.Material or openmc.Cell or openmc.Universe or
-            openmc.Mesh
+        domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.Mesh
             The domain for spatial homogenization
         domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
             The domain type for spatial homogenization
@@ -1491,7 +1490,10 @@ class MGXS(object):
                 distribcell_paths=distribcell_paths)
 
             # Remove nuclide column since it is homogeneous and redundant
-            df.drop('nuclide', axis=1, inplace=True)
+            if self.domain_type == 'mesh':
+                df.drop('nuclide', axis=1, level=0, inplace=True)
+            else:
+                df.drop('nuclide', axis=1, inplace=True)
 
         # If the user requested a specific set of nuclides
         elif self.by_nuclide and nuclides != 'all':