diff --git a/docs/source/methods/neutron_physics.rst b/docs/source/methods/neutron_physics.rst
index 70ace4a353..0b3b9aa594 100644
--- a/docs/source/methods/neutron_physics.rst
+++ b/docs/source/methods/neutron_physics.rst
@@ -278,7 +278,7 @@ channel. Other absorption reactions like :math:`(n,\gamma)` or
 :math:`(n,\alpha)`, on the contrary, produce no neutrons. There are a few other
 idiosyncrasies in treating fission. In an eigenvalue calculation, secondary
 neutrons from fission are only "banked" for use in the next generation rather
-than being tracked as secondary neutrons from elastic and inelastic scattering
+than being tracked as secondary neutrons as elastic and inelastic scattering
 would be. On top of this, fission is sometimes broken into first-chance fission,
 second-chance fission, etc. The nuclear data file either lists the partial
 fission reactions with secondary energy distributions for each one, or a total
@@ -306,8 +306,8 @@ interpolation law. The number of prompt neutrons released per fission event
 :math:`\nu_p` is also given as a function of incident energy and can be
 specified in a polynomial or tabular format. The number of delayed neutrons
 released per fission event :math:`\nu_d` can only be specified in a tabular
-format. In practice, we only need to determine :math:`nu_t` and
-:math:`nu_d`. Once these have been determined, we can calculated the delayed
+format. In practice, we only need to determine :math:`\nu_t` and
+:math:`\nu_d`. Once these have been determined, we can calculate the delayed
 neutron fraction
 
 .. math::
diff --git a/docs/source/usersguide/processing.rst b/docs/source/usersguide/processing.rst
index 3103b7b7cf..70cfe8701e 100644
--- a/docs/source/usersguide/processing.rst
+++ b/docs/source/usersguide/processing.rst
@@ -71,12 +71,12 @@ generation, and particle number of the desired particle. For example, to create
 a track file for particle 4 of batch 1 and generation 2::
 
   settings = openmc.Settings()
-  settings.track = (1, 2, 4)
+  settings.track = [(1, 2, 4)]
 
 To specify multiple particles, the length of the iterable should be a multiple
 of three, e.g., if we wanted particles 3 and 4 from batch 1 and generation 2::
 
-  settings.track = (1, 2, 3, 1, 2, 4)
+  settings.track = [(1, 2, 3), (1, 2, 4)]
 
 After running OpenMC, the working directory will contain a file of the form
 "track_(batch #)_(generation #)_(particle #).h5" for each particle tracked.