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Use openmc.config['cross_sections'] instead of OPENMC_CROSS_SECTIONS

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This commit is contained in:
Paul Romano 2022-08-31 22:13:54 -05:00
parent c29fb407d5
commit a074e0a5cf
8 changed files with 51 additions and 69 deletions
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10
openmc/material.py
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@ -1310,9 +1310,8 @@ class Materials(cv.CheckedList):
"""Collection of Materials used for an OpenMC simulation.
This class corresponds directly to the materials.xml input file. It can be
thought of as a normal Python list where each member is a
:class:`Material`. It behaves like a list as the following example
demonstrates:
thought of as a normal Python list where each member is a :class:`Material`.
It behaves like a list as the following example demonstrates:
>>> fuel = openmc.Material()
>>> clad = openmc.Material()
@ -1330,9 +1329,8 @@ class Materials(cv.CheckedList):
----------
cross_sections : str or path-like
Indicates the path to an XML cross section listing file (usually named
cross_sections.xml). If it is not set, the
:envvar:`OPENMC_CROSS_SECTIONS` environment variable will be used for
continuous-energy calculations and
cross_sections.xml). If it is not set, openmc.config['cross_sections']
will be used for continuous-energy calculations and
:envvar:`OPENMC_MG_CROSS_SECTIONS` will be used for multi-group
calculations to find the path to the HDF5 cross section file.