Style and spacing changes

paulromano · Jan 12, 2023 · Sep 13, 2021 · Sep 13, 2022 · Sep 13, 2022 · Sep 13, 2022
commit 4eda693133a3a0f6c55eea084ca7ddeb3ab0769d
diff --git a/docs/source/methods/cross_sections.rst b/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`_.
-
-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.
+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.
 
 ----------------
 Multi-Group Data

diff --git a/docs/source/usersguide/install.rst b/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)
 

diff --git a/docs/source/usersguide/materials.rst b/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

diff --git a/include/openmc/physics.h b/include/openmc/physics.h
@@ -96,8 +96,9 @@ void inelastic_scatter(const Nuclide& nuc, const Reaction& rx, Particle& p);
 
 void sample_secondary_photons(Particle& p, int i_nuclide);
 
-// ！Split or Roulette particles based their weight and the lower weight window
-//  bound.
+//! Split or Roulette particles based their weight and the lower weight window
+//! bound.
+//
 //! \param[in] p, particle to be split or rouletted with the weight window.
 void split_particle(Particle& p);
 

diff --git a/tests/regression_tests/ncrystal/test.py b/tests/regression_tests/ncrystal/test.py
@@ -1,3 +1,5 @@
+from math import pi
+
 import numpy as np
 import openmc
 import openmc.lib
@@ -9,6 +11,7 @@
     not openmc.lib._ncrystal_enabled(),
     reason="NCrystal materials are not enabled.")
 
+
 def pencil_beam_model(cfg, E0, N):
     """Return an openmc.Model() object for a monoenergetic pencil
      beam hitting a 1 mm sphere filled with the material defined by
@@ -24,7 +27,7 @@ def pencil_beam_model(cfg, E0, N):
     sample_sphere = openmc.Sphere(r=0.1)
     outer_sphere = openmc.Sphere(r=100, boundary_type="vacuum")
     cell1 = openmc.Cell(region=-sample_sphere, fill=m1)
-    cell2_region= +sample_sphere & -outer_sphere
+    cell2_region = +sample_sphere & -outer_sphere
     cell2 = openmc.Cell(region=cell2_region, fill=None)
     geometry = openmc.Geometry([cell1, cell2])
 
@@ -48,7 +51,7 @@ def pencil_beam_model(cfg, E0, N):
     tally1 = openmc.Tally(name="angular distribution")
     tally1.scores = ["current"]
     filter1 = openmc.SurfaceFilter(sample_sphere)
-    filter2 = openmc.PolarFilter(np.linspace(0, np.pi, 180+1))
+    filter2 = openmc.PolarFilter(np.linspace(0, pi, 180+1))
     filter3 = openmc.CellFromFilter(cell1)
     tally1.filters = [filter1, filter2, filter3]
     tallies = openmc.Tallies([tally1])
@@ -66,11 +69,12 @@ def _get_results(self):
             df = tal.get_pandas_dataframe()
         return df.to_string()
 
+
 def test_ncrystal():
-    NParticles = 100000
-    T = 293.6 # K
-    E0 = 0.012 # eV
+    n_particles = 100000
+    T = 293.6  # K
+    E0 = 0.012  # eV
     cfg = 'Al_sg225.ncmat'
-    test = pencil_beam_model(cfg, E0, NParticles)
+    test = pencil_beam_model(cfg, E0, n_particles)
     harness = NCrystalTest('statepoint.10.h5', model=test)
     harness.main()