Fixed in NCrystal docs

docs/source/methods/cross_sections.rst

@@ -190,8 +190,8 @@ and further extend the physics `using plugins`_. Thermal scattering kernels are
 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 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.

docs/source/usersguide/materials.rst

@@ -127,8 +127,8 @@ defines a material containing polycrystalline alumnium,
 defines an oriented germanium single crystal with 40 arcsec mosaicity.
 
 NCrystal only handles low energy neutron interactions. Other interaction are
-provided by standard ACE files. NCrystal_ comes with a `predefined library
-https://github.com/mctools/ncrystal/wiki/Data-library`_ but more materials can
+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 created.