diff --git a/docs/source/methods/cross_sections.rst b/docs/source/methods/cross_sections.rst index c700b3f2d..64e4fac3d 100644 --- a/docs/source/methods/cross_sections.rst +++ b/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. diff --git a/docs/source/usersguide/materials.rst b/docs/source/usersguide/materials.rst index 1886a772b..1eaae846c 100644 --- a/docs/source/usersguide/materials.rst +++ b/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 +`_ 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.