diff --git a/docs/source/methods/cross_sections.rst b/docs/source/methods/cross_sections.rst
index 9c11d3626d..869040f5df 100644
--- a/docs/source/methods/cross_sections.rst
+++ b/docs/source/methods/cross_sections.rst
@@ -75,7 +75,7 @@ are represented using a multi-group library format specific to the OpenMC code.
 The format is described in the :ref:`mgxs_lib_spec`.
 The data itself can be prepared via traditional paths or directly from a
 continuous-energy OpenMC calculation by use of the Python API as is shown in the
-Python API :ref:`_notebook_mgxs_part_iv` example notebook. This multi-group
+:ref:`notebook_mgxs_part_iv` example notebook. This multi-group
 library consists of meta-data (such as the energy group structure) and multiple
 `xsdata` objects which contains the required microscopic or macroscopic
 multi-group data.
@@ -83,9 +83,10 @@ multi-group data.
 At a minimum, the library must contain the absorption cross section
 (:math:`\sigma_{a,g}`) and a scattering matrix. If the problem is an eigenvalue
 problem then all fissionable materials must also contain either
-a fission production matrix cross section (:math:`\nu\sigma_{f,g\arrow\g'}`), or
-both the fission spectrum data (:math:`\chi{g'}`) and a fission production cross
-section (:math:`\nu\sigma_{f,g}`), or, .  The library must also contain
+a fission production matrix cross section
+(:math:`\nu\sigma_{f,g\rightarrow g'}`), or
+both the fission spectrum data (:math:`\chi_{g'}`) and a fission production
+cross section (:math:`\nu\sigma_{f,g}`), or, .  The library must also contain
 the fission cross section (:math:`\sigma_{f,g}`) or the fission energy release
 cross section (:math:`\kappa\sigma_{f,g}`) if the associated tallies are
 required by the model using the library.
@@ -113,8 +114,8 @@ reaction has occurred:
 
 .. math::
 
-    multiplicity_{g \arrow g'} = \frac{\nu_{scatter}\sigma_{s,g \arrow g'}}{
-    								   \sigma_{s,g \arrow g'}}
+    multiplicity_{g \rightarrow g'} = \frac{\nu_{scatter}\sigma_{s,g \rightarrow g'}}{
+    								   \sigma_{s,g \rightarrow g'}}
 
 If this scattering multiplication information is not provided in the library
 then no weight adjustment will be performed. This is equivalent to neglecting
@@ -130,7 +131,7 @@ follows:
 
 .. math::
 
-    \sigma_{a,g} = \sigma_{t,g} - \sum_{g'}{\nu_{scatter}\sigma_{s,g \arrow g'}}
+    \sigma_{a,g} = \sigma_{t,g} - \sum_{g'}\nu_{scatter}\sigma_{s,g \rightarrow g'}
 
 The above method is the same as is usually done with most deterministic solvers.
 Note that this method is less accurate than using the scattering multiplication
diff --git a/docs/source/methods/physics.rst b/docs/source/methods/physics.rst
index e08965371c..bb26ffec53 100644
--- a/docs/source/methods/physics.rst
+++ b/docs/source/methods/physics.rst
@@ -87,7 +87,7 @@ Elastic Scattering
 
 Note that the multi-group mode makes no distinction between elastic or
 inelastic scattering reactions. The spceific multi-group scattering
-implementation is discussed in the multi-group-scatter_ section.
+implementation is discussed in the :ref:`multi-group-scatter` section.
 
 Elastic scattering refers to the process by which a neutron scatters off a
 nucleus and does not leave it in an excited. It is referred to as "elastic"
@@ -182,7 +182,7 @@ Inelastic Scattering
 
 Note that the multi-group mode makes no distinction between elastic or
 inelastic scattering reactions. The spceific multi-group scattering
-implementation is discussed in the multi-group-scatter_ section.
+implementation is discussed in the :ref:`multi-group-scatter` section.
 
 The major algorithms for inelastic scattering were described in previous
 sections. First, a scattering cosine is sampled using the algorithms in
@@ -202,7 +202,7 @@ secondary photons from nuclear de-excitation are tracked in OpenMC.
 
 Note that the multi-group mode makes no distinction between elastic or
 inelastic scattering reactions. The specific multi-group scattering
-implementation is discussed in the multi-group-scatter_ section.
+implementation is discussed in the :ref:`multi-group-scatter` section.
 
 These types of reactions are just treated as inelastic scattering and as such
 are subject to the same procedure as described in :ref:`inelastic-scatter`. For
@@ -229,13 +229,13 @@ incoming energy group is to select a random number (:math:`\xi`) between 0 and
 produced from the outgoing group (`g'`) data for the given incoming group (`g`):
 
 .. math::
-    CDF = \sum_{g'=0}^{h}\Sigma_{s,g \arrow g'}
+    CDF = \sum_{g'=0}^{h}\Sigma_{s,g \rightarrow g'}
 
 If the scattering data is represented as a Legendre expansion, then the
-value of :math:`\Sigma_{s,g \arrow g'}` above is simply the 0th order for the
+value of :math:`\Sigma_{s,g \rightarrow g'}` above is the 0th order forthe
 given group transfer. If the data is provided as tabular or histogram data, then
-the value of :math:`\Sigma_{s,g \arrow g'}` is the sum of all bins of data for a
-given `g` and `g'` pair.
+:math:`\Sigma_{s,g \rightarrow g'}` is the sum of all bins of data for a given
+`g` and `g'` pair.
 
 Now that the outgoing energy is known the change-in-angle, :math:`\mu` can be
 determined. If the data is provided as a Legendre expansion, this is done by