Style and spacing changes

docs/source/methods/cross_sections.rst

@@ -182,19 +182,22 @@ been selected. There are three methods available:
 NCrystal materials
 ------------------
 
-As an alternative of the standard thermal scattering treatment using :math:`S(\alpha,\beta)`
-tables, OpenMC allows to create materials using NCrystal_. In addition to the regular thermal elastic,
-and thermal inelastic processes, NCrystal allows the generation of models for materials that 
-cannot currently included in ACE files such as oriented single crystals (see the `NCrystal paper`_),
-and further extend the physics `using plugins`_. Thermal scattering kernels are generated on
-the fly from dynamic and structural data, or loaded from :math:`S(\alpha,\beta)` tables converted
-from ENDF6 evaluations. These kernels are sampled in a direct way using a fast `rejection algorithm`_ 
-that does not require previous processing. A `large library`_ of materials is already included in
-the NCrystal distribution, and new materials can be easily defined from scratch in the `NCMAT format`_
-or `combining existing files`_.
+As an alternative of the standard thermal scattering treatment using
+:math:`S(\alpha,\beta)` tables, OpenMC allows to create materials using
+NCrystal_. In addition to the regular thermal elastic, and thermal inelastic
+processes, NCrystal allows the generation of models for materials that cannot
+currently included in ACE files such as oriented single crystals (see the
+`NCrystal paper`_), and further extend the physics `using plugins`_. Thermal
+scattering kernels are generated on the fly from dynamic and structural data, or
+loaded from :math:`S(\alpha,\beta)` tables converted from ENDF6 evaluations.
+These kernels are sampled in a direct way using a fast `rejection algorithm`_
+that does not require previous processing. A `large library`_ of materials is
+already included in the NCrystal distribution, and new materials can be easily
+defined from scratch in the `NCMAT format`_ or `combining existing files`_.
 
-The compositions of the materials defined in NCrystal are passed on to OpenMC all other reactions 
-except for thermal neutron scattering are handled by continuous energy ACE libraries.
+The compositions of the materials defined in NCrystal are passed on to OpenMC
+all other reactions except for thermal neutron scattering are handled by
+continuous energy ACE libraries.
 
 ----------------
 Multi-Group Data

docs/source/usersguide/install.rst

@@ -274,9 +274,10 @@ Prerequisites
     * NCrystal_ library for defining materials with enhanced thermal neutron transport
 
       Adding this option allows the creation of materials from NCrystal, which
-      replaces the scattering kernel treatment of ACE files with a modular, on-the-fly approach.
-      To use it `install <https://github.com/mctools/ncrystal/wiki/Get-NCrystal>`_ and 
-      `initialize <https://github.com/mctools/ncrystal/wiki/Using-NCrystal#setting-up>`_
+      replaces the scattering kernel treatment of ACE files with a modular,
+      on-the-fly approach. To use it `install
+      <https://github.com/mctools/ncrystal/wiki/Get-NCrystal>`_ and `initialize
+      <https://github.com/mctools/ncrystal/wiki/Using-NCrystal#setting-up>`_
       NCrystal and turn on the option in the CMake configuration step:
 
           cmake -DOPENMC_USE_NCRYSTAL=on ..
@@ -374,8 +375,8 @@ OPENMC_USE_DAGMC
   (Default: off)
 
 OPENMC_USE_NCRYSTAL
-  Turns on support for NCrystal materials. NCrystal must be 
-  `installed <https://github.com/mctools/ncrystal/wiki/Get-NCrystal>`_ and 
+  Turns on support for NCrystal materials. NCrystal must be
+  `installed <https://github.com/mctools/ncrystal/wiki/Get-NCrystal>`_ and
   `initialized <https://github.com/mctools/ncrystal/wiki/Using-NCrystal#setting-up>`_.
   (Default: off)
 

docs/source/usersguide/materials.rst

@@ -105,12 +105,14 @@ you would need to add hydrogen and oxygen to a material and then assign the
 Adding NCrystal materials
 -------------------------
 
-Additional support for thermal scattering can be added by using NCrystal_.
-The :meth:`Material.from_ncrystal` class method generates a :class:`openmc.Material` object from
-an `NCrystal configuration string <https://github.com/mctools/ncrystal/wiki/Using-NCrystal#uniform-material-configuration-syntax>`_.
-Temperature, material composition, and density are passed from the configuration string
-and the `NCMAT file <https://github.com/mctools/ncrystal/wiki/NCMAT-format>`_
-that define the material, e.g.::
+Additional support for thermal scattering can be added by using NCrystal_. The
+:meth:`Material.from_ncrystal` class method generates a :class:`openmc.Material`
+object from an `NCrystal configuration string
+<https://github.com/mctools/ncrystal/wiki/Using-NCrystal#uniform-material-configuration-syntax>`_.
+Temperature, material composition, and density are passed from the configuration
+string and the `NCMAT file
+<https://github.com/mctools/ncrystal/wiki/NCMAT-format>`_ that define the
+material, e.g.::
 
    mat = openmc.Material.from_ncrystal('Al_sg225.ncmat;temp=300K')
 
@@ -125,12 +127,12 @@ defines a material containing polycrystalline alumnium,
 defines an oriented germanium single crystal with 40 arcsec mosaicity.
 
 NCrystal only handles low energy neutron interactions. Other interactions are
-provided by standard ACE files. NCrystal_ comes with a `predefined library 
+provided by standard ACE files. NCrystal_ comes with a `predefined library
 <https://github.com/mctools/ncrystal/wiki/Data-library>`_ but more materials can
 be added by creating NCMAT files or on-the-fly in the configuration string.
 
-.. warning:: Currently, NCrystal_ materials cannot be modified after they are created. 
-             Density, temperature and composition should be defined in the 
+.. warning:: Currently, NCrystal_ materials cannot be modified after they are created.
+             Density, temperature and composition should be defined in the
              configuration string or the NCMAT file.
 
 .. _NCrystal: https://github.com/mctools/ncrystal