Move scripts in data/ folder to scripts/

data/readme.rst

@@ -1,37 +0,0 @@
-========================
-cross_sections.xml Files
-========================
-
-As a reminder, in order to run a simulation with OpenMC, you will need cross
-section data for each nuclide in your problem. OpenMC is not currently
-distributed with cross section data, so you will have to obtain cross section
-data by other means. The `user's guide`_ offers some helpful advice on how you
-can obtain cross sections.
-
-When OpenMC starts up, it needs a cross_sections.xml file that tells it where to
-find ACE format cross sections. The files in this directory are configured to
-work with a few common cross section sources.
-
-- **cross_sections_ascii.xml** -- This file matches ENDF/B-VII.0 cross sections
-    distributed with MCNP5 / MCNP6 beta.
-
-- **cross_sections_nndc.xml** -- This file matches ENDF/B-VII.1 cross sections
-    distributed from the `NNDC website`_.
-
-- **cross_sections_serpent.xml** -- This file matches ENDF/B-VII.0 cross
-    sections distributed with Serpent 1.1.7.
-
-- **cross_sections.xml** - This file matches ENDF/B-VII.0 cross sections
-    distributed with MCNP5 / MCNP6 beta *that have been converted to binary*.
-
-To use any of these files, you need to follow two steps:
-
-1. Change the path on the ``<directory>`` element in the cross_sections.xml file
-to the directory containing the ACE files.
-
-2. Enter the absolute path of the cross_sections.xml on the ``<cross_sections>``
-element in your settings.xml, or set the CROSS_SECTIONS environment variable to
-the full path of the cross_sections.xml file.
-
-.. _user's guide: http://mit-crpg.github.io/openmc/usersguide/install.html#cross-section-configuration
-.. _NNDC website: http://www.nndc.bnl.gov/endf/b7.1/acefiles.html

docs/source/usersguide/install.rst

@@ -439,13 +439,11 @@ extract the ACE data, fix any deficiencies, and create an HDF5 library:
 
 .. code-block:: sh
 
-    cd openmc/data
-    python get_nndc_data.py
+    openmc-get-nndc-data
 
 At this point, you should set the :envvar:`OPENMC_CROSS_SECTIONS` environment
-variable to the absolute path of the file
-``openmc/data/nndc_hdf5/cross_sections.xml``. This cross section set is used by
-the test suite.
+variable to the absolute path of the file ``nndc_hdf5/cross_sections.xml``. This
+cross section set is used by the test suite.
 
 Using JEFF Cross Sections from OECD/NEA
 ---------------------------------------
@@ -456,12 +454,10 @@ and extract the ACE data, fix any deficiencies, and create an HDF5 library.
 
 .. code-block:: sh
 
-    cd openmc/data
-    python get_jeff_data.py
+    openmc-get-jeff-data
 
 At this point, you should set the :envvar:`OPENMC_CROSS_SECTIONS` environment
-variable to the absolute path of the file
-``openmc/data/jeff-3.2-hdf5/cross_sections.xml``.
+variable to the absolute path of the file ``jeff-3.2-hdf5/cross_sections.xml``.
 
 Using Cross Sections from MCNP
 ------------------------------
@@ -473,8 +469,7 @@ format, run the following:
 
 .. code-block:: sh
 
-    cd openmc/data
-    python convert_mcnp_endf70.py /path/to/mcnpdata/
+    openmc-convert-mcnp70-data /path/to/mcnpdata/
 
 where ``/path/to/mcnpdata`` is the directory containing the ``endf70[a-k]``
 files.
@@ -484,8 +479,7 @@ the following script:
 
 .. code-block:: sh
 
-    cd openmc/data
-    python convert_mcnp_endf71.py /path/to/mcnpdata
+    openmc-convert-mcnp71-data /path/to/mcnpdata
 
 where ``/path/to/mcnpdata`` is the directory containing the ``endf71x`` and
 ``ENDF71SaB`` directories.
@@ -502,16 +496,16 @@ that are to be converted:
 
 1. List each ACE library as a positional argument. This is very useful in
    conjunction with the usual shell utilities (ls, find, etc.).
-2. Use the --xml option to specify a pre-v0.9 cross_sections.xml file.
-3. Use the --xsdir option to specify a MCNP xsdir file.
-4. Use the --xsdata option to specify a Serpent xsdata file.
+2. Use the ``--xml`` option to specify a pre-v0.9 cross_sections.xml file.
+3. Use the ``--xsdir` option to specify a MCNP xsdir file.
+4. Use the ``--xsdata`` option to specify a Serpent xsdata file.
 
 The script does not use any extra information from cross_sections.xml/ xsdir/
 xsdata files to determine whether the nuclide is metastable. Instead, the
---metastable argument can be used to specify whether the ZAID naming convention
-follows the NNDC data convention (1000*Z + A + 300 + 100*m), or the MCNP data
-convention (essentially the same as NNDC, except that the first metastable state
-of Am242 is 95242 and the ground state is 95642).
+``--metastable`` argument can be used to specify whether the ZAID naming
+convention follows the NNDC data convention (1000*Z + A + 300 + 100*m), or the
+MCNP data convention (essentially the same as NNDC, except that the first
+metastable state of Am242 is 95242 and the ground state is 95642).
 
 The ``openmc-ace-to-hdf5`` script has the following command-line flags: