mit-crpg / opendeplete

A depletion framework for OpenMC
MIT License
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OpenMC <cross_sections> element in materials.xml files #21

Closed wbinventor closed 7 years ago

wbinventor commented 7 years ago

The <cross_sections> element is currently included in the OpenMC "materials.xml" files created by OpenDeplete. Is there a reason for doing this? This is unnecessary if the OPENMC_CROSS_SECTIONS environment variable is defined to point to the path for the desired cross section library. We might consider eliminating the <cross_sections> element to make the XML files generated by OpenDeplete more portable across (1) platforms and (2) between users.