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Fix a few mistakes in user's guide xs config section
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1 changed files with 8 additions and 8 deletions
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@ -31,7 +31,7 @@ Environment Variables
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When :ref:`scripts_openmc` is run, it will look for several environment
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variables that indicate where cross sections can be found. While the location of
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cross sections can also be indicated through the
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:attr:`openmc.Materials.cross_setion` attribute (or in the :ref:`materials.xml
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:attr:`openmc.Materials.cross_section` attribute (or in the :ref:`materials.xml
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<io_materials>` file), if you always use the same set of cross section data, it
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is often easier to just set an environment variable that will be picked up by
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default every time OpenMC is run. The following environment variables are used:
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@ -39,14 +39,14 @@ default every time OpenMC is run. The following environment variables are used:
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:envvar:`OPENMC_CROSS_SECTIONS`
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Indicates the path to the :ref:`cross_sections.xml <io_cross_sections>`
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summary file that is used to locate HDF5 format cross section libraries if the
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user has not specified :attr:`Materials.cross_sections` (equivalently, the
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:ref:`cross_sections` in :ref:`materials.xml <io_materials>`).
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user has not specified :attr:`openmc.Materials.cross_sections` (equivalently,
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the :ref:`cross_sections` in :ref:`materials.xml <io_materials>`).
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:envvar:`OPENMC_MG_CROSS_SECTIONS`
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Indicates the path to the an :ref:`HDF5 file <io_mgxs_library>` that contains
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Indicates the path to an :ref:`HDF5 file <io_mgxs_library>` that contains
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multi-group cross sections if the user has not specified
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:attr:`Materials.cross_sections` (equivalently, the :ref:`cross_sections` in
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:ref:`materials.xml <io_materials>`).
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:attr:`openmc.Materials.cross_sections` (equivalently, the
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:ref:`cross_sections` in :ref:`materials.xml <io_materials>`).
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To set these environment variables persistently, export them from your shell
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profile (``.profile`` or ``.bashrc`` in bash_).
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@ -75,8 +75,8 @@ Manually Creating a Library from ACE files
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.. currentmodule:: openmc.data
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The scripts described above use the :mod:`openmc.data` module in the Python API
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to convert ACE data and create a :ref:`cross_sections.xml <io_cross_sections>`
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The :mod:`openmc.data` module in the Python API enables users to directly
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convert ACE data and create a :ref:`cross_sections.xml <io_cross_sections>`
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file. For those who prefer to use the API directly, the
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:class:`openmc.data.IncidentNeutron` and :class:`openmc.data.ThermalScattering`
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classes can be used to read ACE data and convert it to HDF5. For
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