diff --git a/docs/source/conf.py b/docs/source/conf.py
index 4a18f14de..05559aab0 100644
--- a/docs/source/conf.py
+++ b/docs/source/conf.py
@@ -27,6 +27,7 @@ sys.path.insert(0, os.path.abspath('../..'))
 extensions = ['sphinx.ext.autodoc',
               'sphinx.ext.napoleon',
               'sphinx.ext.pngmath',
+              'sphinx.ext.autosummary',
               'sphinxcontrib.tikz',
               'sphinx_numfig',
               'notebook_sphinxext']
diff --git a/docs/source/pythonapi/mgxs.rst b/docs/source/pythonapi/mgxs.rst
index 04e2a99de..c7084e565 100644
--- a/docs/source/pythonapi/mgxs.rst
+++ b/docs/source/pythonapi/mgxs.rst
@@ -4,5 +4,63 @@
 Multi-Group Cross Sections
 ==========================
 
-.. automodule:: openmc.mgxs.mgxs
-    :members: MGXS
+.. currentmodule:: openmc.mgxs.mgxs
+
+----------------------------
+Summary of Available Classes
+----------------------------
+
+.. autosummary::
+
+   MGXS
+   AbsorptionXS
+   CaptureXS
+   Chi
+   FissionXS
+   NuFissionXS
+   NuScatterXS
+   NuScatterMatrixXS
+   ScatterXS
+   ScatterMatrixXS
+   TotalXS
+   TransportXS
+
+-------------------
+Class Documentation
+-------------------
+
+.. autoclass:: MGXS
+    :members:
+
+.. autoclass:: AbsorptionXS
+    :members:
+
+.. autoclass:: CaptureXS
+    :members:
+
+.. autoclass:: Chi
+    :members:
+
+.. autoclass:: FissionXS
+    :members:
+
+.. autoclass:: NuFissionXS
+    :members:
+
+.. autoclass:: NuScatterXS
+    :members:
+
+.. autoclass:: NuScatterMatrixXS
+    :members:
+
+.. autoclass:: ScatterXS
+    :members:
+
+.. autoclass:: ScatterMatrixXS
+    :members:
+
+.. autoclass:: TotalXS
+    :members:
+
+.. autoclass:: TransportXS
+    :members:
diff --git a/docs/source/pythonapi/opencg_compatible.rst b/docs/source/pythonapi/opencg_compatible.rst
index c8ba82e8c..c807e19cc 100644
--- a/docs/source/pythonapi/opencg_compatible.rst
+++ b/docs/source/pythonapi/opencg_compatible.rst
@@ -1,8 +1,8 @@
-.. _pythonapi_openmc_mgxs:
+.. _pythonapi_opencg_compatible:
 
-==========================
-Multi-Group Cross Sections
-==========================
+====================
+OpenCG Compatibility
+====================
 
-.. automodule:: openmc.mgxs.mgxs
+.. automodule:: openmc.opencg_compatible
     :members:
diff --git a/openmc/filter.py b/openmc/filter.py
index 8a5525233..5c0343df7 100644
--- a/openmc/filter.py
+++ b/openmc/filter.py
@@ -511,8 +511,9 @@ class Filter(object):
             surface, material or universe ID corresponding to each filter bin.
 
             For 'distribcell' filters, the DataFrame either includes:
-            1) a single column with the cell instance IDs (without summary info)
-            2) separate columns for the cell IDs, universe IDs, and lattice IDs
+
+            1. a single column with the cell instance IDs (without summary info)
+            2. separate columns for the cell IDs, universe IDs, and lattice IDs
                and x,y,z cell indices corresponding to each (with summary info).
 
             For 'energy' and 'energyout' filters, the DataFrame include a single
diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py
index 215b4f12e..13537848e 100644
--- a/openmc/mgxs/library.py
+++ b/openmc/mgxs/library.py
@@ -324,9 +324,7 @@ class Library(object):
         ----------
         domain : Material or Cell or Universe or Integral
             The material, cell, or universe object of interest (or its ID)
-        mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission',
-                     'nu-fission', 'scatter', 'nu-scatter', 'scatter matrix',
-                     'nu-scatter matrix', 'chi'}
+        mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission', 'nu-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'}
             The type of multi-group cross section object to return
 
         Returns
diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py
index f0aa9d618..7c2156c19 100644
--- a/openmc/mgxs/mgxs.py
+++ b/openmc/mgxs/mgxs.py
@@ -258,9 +258,7 @@ class MGXS(object):
 
         Parameters
         ----------
-        mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission',
-                     'nu-fission', 'scatter', 'nu-scatter', 'scatter matrix',
-                     'nu-scatter matrix', 'chi'}
+        mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission', 'nu-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'}
             The type of multi-group cross section object to return
         domain : Material or Cell or Universe
             The domain for spatial homogenization
@@ -338,8 +336,8 @@ class MGXS(object):
         """Get the atomic number density in units of atoms/b-cm for a nuclide
         in the cross section's spatial domain.
 
-        Paramters
-        ---------
+        Parameters
+        ----------
         nuclide : str
             A nuclide name string (e.g., 'U-235')
 
@@ -373,8 +371,8 @@ class MGXS(object):
         """Get an array of atomic number densities in units of atom/b-cm for all
         nuclides in the cross section's spatial domain.
 
-        Paramters
-        ---------
+        Parameters
+        ----------
         nuclides : Iterable of str or 'all' or 'sum'
             A list of nuclide name strings (e.g., ['U-235', 'U-238']). The
             special string 'all' will return the atom densities for all nuclides
diff --git a/openmc/tallies.py b/openmc/tallies.py
index 03aa8e3a7..c9e4854e2 100644
--- a/openmc/tallies.py
+++ b/openmc/tallies.py
@@ -1269,7 +1269,7 @@ class Tally(object):
         correspond directly to the two filters with two and four bins.
 
         Parameters
-        ---------
+        ----------
         value : str
             A string for the type of value to return  - 'mean' (default),
             'std_dev', 'rel_err', 'sum', or 'sum_sq' are accepted